~\ jl REGULATORY ~FORMATION DISTRIBUTION 'SY M ('R IDS)

ACCE'8 SION NBR ~ 830 f?20336 DOC y DATE 83/04/1 8 NOTARIZED ~ YES DOCKETFACIL:50-275 Diablo Canyon Nuclear 'Power Planti Unitt fi Pacific Ga 05000275

'SO"323 Diablo Canyon Nuclear Power Plantp Uni,'t 2g Pacific Ga 05000323AUTH~ NAME AUTHOR AFFILIATION

SCHUYLER~J ~ D, '~Pacific Gas L Electric Co,CRANE<P ~ A, tpaci f ic Gas 8 "Eltectr ic Co.'REIC IP ~ NAME! AEC'IP.lENT„AFFILIATION

EISENHUT < D > G, 'D i.v i s i on of Licensing

S UBJECT: For war ds nesponse <to Generic Ltr 82-33''Suppl 1= toNUREG 0737 r e requi rements,f or emergency r esponsecapabi 1 i~ties'N/one oversize encl, Aperture card is.available

DI'STRIBUTION 'CODE.: A003'S >CQPIES )RECEIVED:LTR, iENCL'. ~ " SIZE@~,TITLE: OR/Licensing Submitttal'. Suppl 1 to NUREG 0737(Generic Ltt 82 33)

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ROBERT OHLBACHYICC FA55IDCITT AITD OERCRAL ATIDRRCY

77 BEALE STREET, SAN FRANCISCO, CALIFORNIA 94106P. O. BOX 7442, SAN FRANCISCO, CALIFORNIA 94120

TELEPHONE (415) 781.4211TELECOPIER (415) 543 ~ 7813

CHARLES T, VAN DCVSCNPHILIP A. CRANCI JR.HCNRY J ~ LOPLANTC

JOHN 6 ~ O ISSONARTHVR L ~ HILLMAN,JR,

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April 18, 1983

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Mr. D. G. Eisenhut, DirectorDivision of LicensingOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CcmmissionWashington, DC 20555

Re: Docket No. 50-275, OL-DXR-76Docket No. 50-323Diablo Canyon Units 1 and 2Generic Letter No. 82-33

Dear Mr. Eisenhut:

In accordance with Generic Letter No. 82-33, attached are tentativeschedules for canpletion of the requirEments contained in Supplenent 1 toNUREG&737., These schedules are based upon the best information currentlyavailable.

XIGandH endorses the philosophy of a living integrated schedule.In order to obtain the information necessary to develop that schedule,PGandE is participating with the Nuclear UtilityTask Action Conmittees(NUTACs) and the Westinghouse Owners Group. %hen these organizationscomplete their efforts and publish final documents, XGandE will review thisinformation and, where consistent with XGandH goals, will use it to developthe integrated schedule. XGandE will confirm or revise the schedule accompanyingthis submittal within 30 days after publication of the final documents.XGandH requests that the confirmatory order not be issued until we have hadthe opportunity to confirm or revise these tentative schedules.

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Kindly acknowledge receipt of this material on the enclosed copyof this letter and return it in the enclosed addressed envelope.

Subscribed to in San Francisco, California, this 18th day ofApril, 1983.

Respectfully submitted,

Pacific Gas and Electric Company

Byames 0. Schuyler

Vice PresidentNuclear Power Generation

Robert OhlbachPhilip A. Crane, Jr.Richard F. LockeAttorneys for PacificGas nd Electric Company

Subscribed and sworn to before methis 18th day of April, 1983

B i ip . Crane,

cy J. Lenaster, N licin and for the City and County ofSan Francisco, State of California

My Commission expires April 14, 1986

SEnL

Enclosure

CC: Mr. John B. Martin, NRC Region VService List

XXXXXXXXXXXXXXXXXXXXXXXXXXXXX

i.s . NANCY J. LEMASTERNOTARY PUBLIC.CALIFORNIA Ic

'jgP~~ CITY ANO COUNTY OFPA SAN FRANCISCO K

M~ CammIssID~ Ex~Ires A~rII i4kcxxxxxxxxxxxxxxxxxxxxxxxxxxxÃ

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PGandE's RESPONSETO

GENERIC LETTER 82-33(SUPPLEMENT 1 TO NUREG-0737)

1. INTRODUCTION

On December 17, 1982 the NRC Staff issued Generic Letter 82-33,Supplement 1 to NUREG-0737 which provided requirements for emergencyresponse capabilities and replaced the corresponding requirements inNUREG-0737. The requirements contained in Supplement 1 to NUREG-0737 areunique in that they do not specify completion dates. Supplement 1 toNUREG-0737 recognizes the difficulties of implementing generic deadlinesand instead, permits the development of plant specific schedules whichtake into consideration the unique status of each plant. PGandE endorsesthat philosophy and consistent with it intends to develop a livinginteg} ated schedule. This schedule will include the items related toemergency response capabilities and, in the long term, any newrequirements imposed by the NRC and any items PGandE considers necessaryto improve the, performance of the Diablo Canyon Power Plant. PGandE hasnot completed the development of this integrated schedule; however, thissubmittal contains tentative schedules which are expected to remainunchanged when the integrated schedule is developed.

In order to develop the integrated schedule PGandE is participating inNuclear UtilityTask Action Committees (NUTAC's) and the WestinghouseOwners Group. Where those organizations provide information consistentwith PGandE goals it will be used to develop the integrated schedules.Further details on these industry groups will be provided in the sectionon Implementation and Integration.

PGandE's current efforts to be responsive is a continuation of ourcommitment to comply with NRC requirements as well as theirrecommendations. This was demonstrated by PGandE's r esponsiveness toNUREG-0578 "Short-Term Lessons-Learned Requirements". When GenericLetter 81-10, "Post-TMI Requirement for the Emergency OperationsFacility" and NUREG-0696, "Functional Criteria for Emergency ResponseFacilities" were issued, PGandE evaluated the installed and proposedfacilities and determined that major modifications and upgr ading of ourfacilities and equipment were required to meet those new guidelines.

PGandE designed and commenced construction for a new Emergency Opet ationsFacility to meet the guidelines of NUREG-0696. A contract was awar ded todesign an upgraded Emergency Response Facility Data System which iscurrently being installed. This system includes a Safety ParameterDisplay System (SPDS) for each unit that will be available in both theTechnical Support Center and the Emergency Operations Facility. TheSafety Par ameter Display System was also designed to meet the guidelinesof NUREG-0696. Design and construction efforts were star ted prior toeither the issue of SECY 82-111, "Requirements for Emergency ResponseCapability" or Generic Letter 82-33.

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. II. IMPLEMENTATION AND INTEGRATION

PGandE is participating in a number of industry groups. These groupsinclude the Nuclear UtilityTask Action Committees on SPDS, DetailedControl Room Design Review (DCRDR), and Emergency Response Capabilities;and the Westinghouse Owners Groups for Emergency Response Guidelines andEmergency Response Guidelines Systems Review and Task Analysis.

The NUTAC's were formed to define industry'positions on the key issues ofGeneric Letter 82-33. The NUTAC on Emergency Response Capabilities isdeveloping guidelines for the following'.

II

Regulatory Guide 1.97, Rev. 2 (AMI) instrumentationimplementation.Guidance for an integrated emergency response capabilityimplementation plan.Component verification and system validation.Implementation of emergency response facilities.

The NUTAC for the SPDS has completed its effort; however, the NUTAC's forEmergency Response Capability and Detailed Control Room Design Review arenot scheduled to issue their final documents until June 1983.

The Westinghouse Owners Group is presently preparing Revision 1 to thegeneric technica'l guidelines for NRC review. These generic technicalguide'lines, when approved, will be used to develop plant-specificemergency operating procedures.

PGandE has reviewed the drafts of some of these documents; and, whereconsistent with PGandE's goals, they were used to assist in thescheduling of the requirements specified in Supplement 1. The schedulesthat are provided in this response are based on the best informationavailable; however, until we have had the opportunity to review the finalefforts of the NUTAC's and receive the Westinghouse Owners GroupEmergency Response Guidelines, Revision 1, we are not prepared to havethese schedules used as the basis for a confirmatory order. PGandE doesnot expect to make changes to the schedules contained in this response.However, within thirty days after the final documents are issued, PGandEwill either confirm or submit new schedules as appropriate.

Considerable effort has been expended in meeting the emergency r esponsecapability requirements. The Emergency Response Facilities (ERF s) havebeen designed and are in various stages of construction; the SPDS hasbeen designed, and is being installed and tested; qualifiedinstrumentation has been installed to monitor approximately 75 percent ofthe variables listed in Reg. Guide 1.97, Rev. 2, and negotiations areunder way to obtain consultant services to assist in the DCRDR.

The DCRDR will be used to verify that an effective integration of thecontrol room emergency response capabilities has been achieved. Examplesof how the DCRDR will be used to integrate .the other areas are:

1. The task analysis portion of the DCRDR will interface with thedevelopment of the Emergency Operating Procedures (EOP's).

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2. The control room survey will check the human compatibility of theinstrumentation associated with Reg. Guide 1.97, Rev. 2.

3. The validation phase will be used to check the design of the SPDS.

4. The task analysis will provide input to assist in determiningtraining needs of the control room operators.

5. Following determination of discrepancies and the correspondingresolution, input will be provided to assure necessary retraining andprocedure revision.

III. STATUS OF THE ITEMS SPECIFIED IN GENERIC LETTER 82-33

A. Safety Parameter Display Systems (SPDS)

1. The SPDS at Diablo Canyon Power Plant is one portion of theEmergency Response Facility Data System which is currently beinginstalled and tested in each unit. Installation of the Unit 1

SPDS is nearly completed, and is presently undergoing testing.

The SPDS for each unit is a computer based system consisting of adata acquisition system, two data-handler computers, two videogenerator s located in the Technical Support Center (TSC), and twocolor video monitors located in the Control Room.

The SPDS utilizes a single display for presentation on each ofthe control room monitors. This particular display, termed SPDS,will present several plant parameters in real time in a bar chartformat. This "SPDS display" will contain information whichcontrol room personnel can use to monitor:

Reactivity controlReactor core cooling and heat removal from the primarysystem.

,, - 'eactor coolant system integrity.Radioactivity 'control.Containment conditions.

In addition to the "SPDS display", sixteen other displays areavailable, which include mimics and decision trees.

The DCRDR will be used to check the design basis of the SPDS.

2. A safety analysis describing the basis for the parametersselected for the SPDS and an implementation plan is scheduled tobe submitted by August 1, 1983.

3. The SPDS is scheduled to be operable for Unit 1 by August 1, 1983and for Unit 2 by h'larch 1, 1984.

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Initial operator training on the SPDS is scheduled to becompleted by July 1, 1983. Because of the relationships thatexist between the SPDS, the EOP's and any revisions that may benecessary as a result of the DCRDR; training on the SPDS isexpected to be a continuing effort which would only be completedwhen the EOP's are implemented and the DCRDR is finished.

B. Detailed Control Room Design Review (DCRDR)

In February 1982, PGandE began planning for a DCRDR in responseto NUREG-0700, "Guidelines for Control Room Design Reviews." Amanagement team and a multi-disciplinary review team wereestablished. 1<hen SECY 82-111, "Requirements for EmergencyResponse Capability," was issued, it was considered prudent todelay the commencement of the DCRDR until the requirements hadbeen finalized. Negotiations are now in progress to obtain theservices of a human factors repr esentative (consultant) to be amember of the review team.

2. The DCRDR Program Plan is scheduled to be submitted by August 1,1983.

3. The DCRDR Summary Report is scheduled to be submitted by December31, 1984.

C. Regulatory Guide,1.97( t

PGandE pre'sently complies with Regulatory Guide 1.97 Rev. 2 forapproximately 75/ of the variables in Table 2 of the RegulatoryGuide. Approximately 905 of the instrumentation is installed,but some of it requires replacement with environmentallyqualified devices and/or upgrade to meet other requirements.

At this time devices for measurement of Boric acid charging flow,containment atmosphere temperature, neutron flux, RCS solubleboron concentration, and radioactivity concentration or radiationlevel in circulating primary coolant, which meet allrequirements, are not available. Several other instruments willbe ordered with delivery dates currently estimated to extend toJu'ly 1984. These factors make it very difficult to planinstallation dates and are not factors which can be controlled bythe utility.

2. The report specified in paragraph 6.2 of Supplement 1 toNUREG-0737 is scheduled to be submitted by August 15, 1983 forthe available instrumentation.

D. Emergency Operating Procedures (EOP's)

PGandE is continuing to participate in the Westinghouse OwnersGroup to develop the Generic Emergency Response Guidelines.First drafts of the Diablo Canyon EOP writers guide, validationand verification program, and a technical instruction forpr eparation of EOP's have been completed.

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2. The procedures generation package is scheduled to be submitted byJuly 1, 1983.

3. The EOP's are scheduled to be implemented by July 1, 1984, orwithin one year of the receipt of the revised Westinghouse Owner sGroup's emergency response guidelines whichever occurs later.

E. Integrated Training Plan

1. The necessary training for operators on the SPDS and EOP's isscheduled to be completed 'by July,l, 1984. Any training due tomodifications resulting "from the DCRDR.will be completed afterthe DCRDR is completed.

2. Training on the emergency resp'onse facilities will be conductedafter the facilities are completed.

F. Emergency Response Facilities (ERF's)

1. Technical Support Center (TSC)

A. The TSC has been successfully tested during two full-scaleannual exercises and a number of plant drills. The EmergencyResponse Facility Data System is being added to the TSC toimprove emergency response capabilities. This system is beinginstalled and tested. Training on the system will beconducted after the testing is completed.

B. The TSC is scheduled to be fully functional by September 1,1983, for Unit 1 and by hiarch 1, 1984 for Unit 2.

2. Operational Support Center (OSC)The OSC is fully functional.

3. Emergency Operations Facility (EOF)

a. An interim EOF, consisting of an arrangement of trailers, islocated 11.7 miles from Diablo Canyon at the San Luis ObispoCounty Sheriff's facility. This EOF has been successfullytested during two full-scale annual exercises. The interimEOF meets the intent of the requirements. The EmergencyResponse Facility Data System is being installed in theinterim EOF.

b. A permanent EOF is under construction at the San Luis ObispoCounty Sher iff's facility and will meet Option 2 location andhabitability requirements. The projected completion ofconstruction activities is in December 1983. The EmergencyResponse Facility Data System will be installed in the EOF.

c. The EOF is scheduled to be fully functional for Unit 1 byFebruary 29, 1984 and for Unit 2 by March 31, 1984.

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G. The attached schedu1e i11ustrates in a, bar chart format the basicsequence of events and key intermediate steps necessary to imp1ementthe items specified in Generic Letter 82-33. The graph shows thetentative schedu1ed comp1etion dates and major mi1estones for theitems discussed in this 'letter. This schedu1e is a simp1ifiedversion of the ones that are being used to track the imp1ementationprogress. PGandE present1y intends to uti1ize a simi'lar system tointegrate future NRC requirements and faci1ity improvements.

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