ML17299A731

Forwards Schedule for Implementing Remaining NUREG-0737, Suppl 1 Requirements for Units 1 & 2 SPDS & Unit 2 Emergency Operating Procedures,Emergency Response Facilities & Human Engineering Ddiscrepanices.W/Reg Guide 1.97 Schedule

ML17299A731
Person / Time
Site:	Palo Verde
Issue date:	11/08/1985
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Knighton G Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 ANPP-33943-EEVB, ANPP-33965-EEVB, TAC-56654, NUDOCS 8511120062
Download: ML17299A731 (14)

Text

REGULATOR INFORMATION DISTR IBUTI'ON I STEM (RIDS)DOCKET-0 05000528 05000529

SUBJECT:

Forwards schedule for implementing remaining NUREG 0737'uppl 1-reAuirements for Units 1 L 2 SPDS It Unit 2 emergency operating proceduresiemergency responset facilities 8 human engineering decrepancies.H/Reg Guide 1,97 schedule.DISTRIBUTION CODE: A0030, COPIES RECEIVED:LTR L ENCL'SIZE: TITLE: OR/Licensing Submittal:

Suppl 1, to NUREG-0737(Generic Ltr 82~33)ACCESSION NBR: 8511120062 DOC~DATE: 85/11/08 NOTARIZED:

NO FACIL:STN-50-528 Palo Verde Nuclear Stationi Unit.1E Arizona Publi STN-50-529 Palo Verde Nuclear Stationi Unit 2E ArizonaT Publi AUTH.NAME AUTHOR AFF IL I ATION VAN BRUNTP E~E.'rizona Nucil ear Power Project (f ormer 1 y Arizona Pub I i c Serv RECIP~NAME RECIPIENT AFFILIATION KNIGHTONrG.N.

Of f i ce of, Nuclear Reactor Regul at i one Di rector NOTES:Standardized plant.OL: 12/31/8Q Standardized plant~05000528 05000529 RECIPIENT ID CODE/NAMEI NRR LB3 BCi INTERNAL: ADM/LFMB NRR PAUI SONrN NRR/DHFS/PSRB NRR/DL/ORB5 NRR/DSI/I CSB N I/RAB E FIL EXTERNAL: 20X NRC PDR CO~IES LTTR ENCL 7 7 1 0 1 1 2 2 5 5 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME, IE/DEPER/EPB NRR/DHFS/HFEB NRR/DL/ORABT NRR/DSI/CPB NRR/DSI/METB NR R/D 8 I/R 8 B.RGN5 LPDR NSIC COPIES LTTR ENCL 3 3 5 5 1 1 1 1 1 1 1'1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 3b ENCL 35 1 4 A I., g Arizona Nuclear Power Project P.O.BOX52034 4 PHOENIX,ARIZONA85072-2034 November 8, 1985 ANPP-33965 EEVB/MFQ/JKO Director of Nuclear Reactor Regulation Attention:

Mr.G.M.Knighton, Project Director PWR Project Directorate

/f7 Division of Pressurized tltater Reactor Licensing-B U.S.Nuclear Regulatory Commission Washington, D.C.20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)Units 1 and 2 Schedule of NUREG 0737 Supplement 1 Items Docket Nos.STN-50-528 (License No.NPF-41)/529 File: 85-056-026 G.l.01.10

Dear Mr.Knighton:

The attachments to this letter provide the schedule for implementing the remaining requirements of NUREG 0737 Supplement 1 for PVNGS Unit 2.Attachment 1 provides the schedule for any incomplete items associated with the Safety Parameter Display System, Emergency Operating Procedures and the Emergency Response Facilities.

Attachment 2 provides the schedules for completing the corrections to the Human Engineering Discrepancies (HED's).Finally, Attachment 3 provides the implementation schedule for completing the remaining Regulatory Guide 1.97 Variables.

This letter also addressees the schedule for the audit of the Safety Parameter Display System for Unit 1 and closes out license condition 2.C.(11)(a) for NPF-41.(See attachment 1).If you have any questions or require additional information, please contact tlilliam F.Quinn of my staff.Very truly yours,~/~E.E.Van Brunt, Jr.Executive Vice President Project Director EEVB/JKO/ds Attachments CC: icitra I PDR ADOCK 05000528 85111200b2 851108 M.C.Ley F PDR R.P.Zimmerman A.C.Gehr l l t q*',~J ATTACHMENT 1 1.Safety Parameter Dis la System (SPDS)The SPDS will be ready for an NRC audit by April 30, 1986.Since the SPDS design is identical for Units 1 and 2, both Units will be ready for the audit at the same time.2.Detailed Control Room Desi n Review (DCRDR)The resolutions for the Human Engineering Discrepancies (HED's)and audit findings that were identified as a result of the DCRDR and were required to be corrected prior to fuel load have not been completely implemented into Unit 2.In Attachment 2, there is a list of remaining HED's along with the implementation schedule for the resolutions of the HED's.3.Regulatory Guide 1.97 Revision 2 (R.G.1.97)Instrumentation for the R.G.1.97 variables was described in letters dated August 1, 1984 (ANPP-30092) and December 5, 1984 (ANPP-31334).

For Unit 2, this instrumentation will have been installed, tested and considered functional by fuel load with the exception of the variables listed in Attachment 3.A schedule for completing the testing of only the R.G.1.97 instruments are also provided in Attachment 3.4.Emergency Operating Procedures (EOP's)The requirements of Supplement 1 to NUREG 0737 were to use approved emergency technical guidelines to upgrade the plant specific EOP's.Revision 2 of CEN-152,"Emergency Procedure Guidelines", was approved by the staff in a letter dated April 16, 1985 and subsequently, we have upgraded the PVNGS EOP's to Revision 2.The EOP's for Unit 1 have also been upgraded to Revision 2.Therefore, this letter serves to close out the commitment made in the letter dated July 10, 1985 (ANPP-32987) from ANPP to the NRC.We also consider this item to be complete for Unit 2.5.Emergency Response Facilities (ERF's)The ERF's are complete with the exception of the testing required for the instruments associated with R.G.1.97.0305Z/0014m

~l d ATTACHMENT 2 (HED's)I HED AUDIT I INUMBER FINDINGI ACTION TO CLOSE SCHEDULE REFERENCE LETTER 49C 64C 100C 101B 98C ssc I 172 68B 1.2 1.2 1.2 1.2 1.3 7.7 5.15 7.7 I 1.4 Install non-glare bulbs Install control room car et Feb.15, 1986 Prior to exceed-in 5%ower I Ietter to NRC dated Aug.30, 1985 (ANPP-33802)

I llB 137A 2.5 4.1 5.2 6.2 I 6.13 3.13 6.29 6.30 Install missing nameplates on control boards.Correct wrong nameplates Prior to fuel load I Prior to fuel load Letters to NRC dated June 30, 1983 (ANPP-24212) and March 14, 1984 (ANPP-29066)

Letters to NRC dated June 30, 1983 (ANPP-24212) and March 14, 1984 (ANPP-29066) 79A 6.38 115C 6.43 I 6.45 Install missing mimics and correct some existing ones Prior to fuel load Letter to NRC dated June 30, 1983 t (ANPP-24212) 6.41 Correct color lenses Prior to initial criticalit 128A 72C Install annunciator windows with correct color I 5.33 Adjust slide wire resistors on MCC's Prior to fuel load Prior to exceed-in 5%ower Letter to NRC dated March 14, 1984'ANPP-29066) 4 ,0 I~li"li il I,'I Y I I I I Ii Y I I I I I r, Il W I I II I I II lI~W 3 4 u"-G~II ATTACHMENT 2 (Continued)

I I HED I AUDIT J NUMaERIFINDINC I 151A I 169A I I ACTION TO CLOSE Install writing surfaces at RSP Issue Procedure SCHEDULE Prior to exceed-ing 5X power Prior to exceed-ing 5%power REFERENCE LETTER Letter to NRC dated-Oct 29, 1984 (ANPP-30986) 157A 158A I I 152A I I Install fire detector Install zone markings on RSP Correct Wrong Nameplates on RSP Prior to exceed-ing 5X power Prior to exceed-ing 5X power Prior to exceed-ing 5X power Letter to NRC dated October 29, 1984)(ANPP-30986) ll ATTACHMENT 3 (R.G.1.97)TYPE CATE-GORY VARIABLE Degrees of subcooling Control rod position SCHEDULE Prior to 5X power Prior to initial criticality JUSTIFICATION ICovered under Inadequate-Core Cool-Iing Instrumentation (ICCI)Commit-Iments (SSER 6 II.F.2)I I Instrumentation is installed limmediately after fuel load, prior Ito initial criticality B I B I B C C I c I c C I I c I E I E I E I E E 1 1 3 Core exit temperature Coolant level in reactor RCS solub.Boron Conc.(0-6000)3 3 3 I I I 2 I 2 I I I 2 I I I 2 I I 2 I 2 I 2 I Containment area radiation Radiation exposure rate I Auxiliary building airborn radioactivity Condenser air removal system exhaust Common plant vent discharge any of above Radioactive concentration or radiation level in circulating primary coolant Analysis of'primary coolant II Containment area radiation monitors.Effluent radioactivity-noble gas effluent from condenser air removal system exhaust Containment effluent radioactivity-noble gases from identified release points Radiation exposure rate Effluent radioactivity-noble gases from buildings Prior to 5X power Prior to 5X power I Prior to 5%power Prior to initial criticality Prior to 5%power Prior to Mode 4 Prior to Mode 4 I Prior to Mode 4*I Prior to initial criticality Prior to Mode 4*Prior to Mode 4 Prior to initial I criticality Prior to Mode 4*I Prior to Mode 4 Prior to Mode 4*IPost Accident Sampling System l(ANPP-33573)

INo activity in reactor'coolant Isystem prior to initial criticalityl ICapability provided by PVNGS Grab ISample PASS (ANPP-33573)

ISee Footnotes (1)and (2)ISee Footnotes (1)and (2)I I See Footnote (1)I INo activity prior to initial Icriticality ISee Footnotes (1)and (2)I I ISee Footnotes (1)and (2)INo activity prior to initial Icriticality ISee Footnotes (1)and (2)I ISee Footnotes (1)and (2)ISee Footnote (1)I I*Two of these monitors are required by fuel load per the Tech.Specs.and they will be done exceptions to the Tech.Specs.by fuel load.We are taking no t I'I~.~k~II 1 1 1 I t 1 I t ,I H 1 I I II 1'I il I I HI It tl I th t II 1 ht 1 ti 1 1 I II 1 jl~H t 1 1 d p~I'I C f I~f t I 1 I 4 I I I 1 f.~t~1 1't 1'tp Il II I t It 1 1 I t it d It I II N 4 ATTACHMENT 3'(Continued)

TYPE CATE-, GORY VARIABLE SCHEDULE JUSTIFICATION Vent from steam generator safety relief valves or atmospheric dump valves Radiation exposure meters Primary coolant and sump (grab sample)Prior to mode 4 Prior to initial criticality Prior to exceeding 5X power See Footnotes (1)and (2)No activity prior to initial criticality IPost Accident Sampling System l(ANPP-33573) l I FOOTNOTES: (l)No activity until initial criticality.

These monitors are required by the Technical Specifications prior to Mode 4.(2)This takes exception to NUREG 0737 commitments.

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