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)

ACCESSION NBR: 8511120062 DOC ~ DATE: 85/11/08 NOTARIZED: NO DOCKET- 0 FACIL:STN-50-528 Palo Verde Nuclear Stationi Unit. 1E Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Stationi Unit 2E ArizonaT Publi 05000529 AUTH. NAME AUTHOR AFF ILI ATION VAN BRUNTP E E.'rizona Nucil ear Power Project (f ormer y Arizona Pub i c Serv

~ 1 I RECIP NAME

~ RECIPIENT AFFILIATION KNIGHTONrG.N. Of f i ce of, Nuclear Reactor Regul at i one Di rector

SUBJECT:

Forwards schedule for implementing remaining NUREG 1- reAuirements for Units 1 L 2 SPDS It Unit 2 emergency 0737'uppl 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)

NOTES:Standardized plant. 05000528 OL: 12/31/8Q Standardized plant ~ 05000529 RECIPIENT CO~IES RECIPIENT COPIES ID CODE/NAMEI LTTR ENCL ID CODE/NAME, LTTR ENCL NRR LB3 BCi 7 7 INTERNAL: ADM/LFMB 1 0 IE/DEPER/EPB 3 3 NRR PAUI SONrN 1 1 NRR/DHFS/HFEB 5 5 NRR/DHFS/PSRB 2 2 NRR/DL/ORABT 1 1 NRR/DL/ORB5 5 5 NRR/DSI/CPB 1 1 NRR/DSI/I CSB 1 1 NRR/DSI/METB 1 1 N I/RAB 1 1 NR R/D 8 I /R 8 B. 1

'1 E FIL 1 1 RGN5 1 1 EXTERNAL: 20X 1 1 LPDR NRC PDR 1 1 NSIC 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. 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 85111200b2 851108 I

PDR ADOCK 05000528 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 REFERENCE INUMBER FINDINGI ACTION TO CLOSE SCHEDULE LETTER 49C 1.2 Install non-glare bulbs Feb. 15, 1986 Ietter to NRC dated Aug. 30, 1985 64C 1.2 (ANPP-33802) 100C 1.2 101B 1.2 98C 1.3 7.7 5.15 ssc I 7.7 172 I Prior to exceed-68B 1.4 Install control room car et in 5% ower I 2.5 Install missing nameplates on control boards . Prior to fuel Letters to NRC dated June 30, 1983 4.1 load (ANPP-24212) and March 14, 1984 5.2 (ANPP-29066)

I llB 6.2 I 6.13 3.13 Correct wrong nameplates I Prior to fuel Letters to NRC dated June 30, 1983 6.29 load (ANPP-24212) and March 14, 1984 137A 6.30 (ANPP-29066) 79A 115C I

6.38 6.43 6.45 6.41 Install missing mimics and correct Correct color lenses some existing ones Prior to fuel load Prior to initial Letter to NRC (ANPP-24212) dated June 30, 1983 t

criticalit 128A Install I

annunciator windows with correct color Prior to fuel Letter to NRC dated March 14, 1984 load 'ANPP-29066) 72C 5.33 Adjust slide wire resistors on MCC's Prior to exceed-in 5% ower

"li 4 ,0 I

~ li il I,'I I I Y

I I

Y Ii I

I I

I I

r, Il I

W I

I lI 4

I

~ W 3 u "- G ~

II II II

ATTACHMENT 2 (Continued)

I I HED I AUDIT REFERENCE J NUMaERIFINDINCI ACTION TO CLOSE SCHEDULE LETTER 151A Install writing surfaces at RSP Prior to exceed- Letter to NRC dated-Oct 29, 1984 ing 5X power (ANPP-30986)

I 169A Issue Procedure Prior to exceed-I I ing 5% power 157A I Install fire detector Prior to exceed- Letter to NRC dated October 29, 1984) ing 5X power (ANPP-30986) 158A Install zone markings on RSP Prior to exceed-I I ing 5X power 152A I Correct Wrong Nameplates on RSP Prior to exceed-ing 5X power

ll ATTACHMENT 3 (R.G. 1.97)

CATE-TYPE GORY VARIABLE SCHEDULE JUSTIFICATION Degrees of subcooling Prior to 5X power ICovered under Inadequate-Core Cool-Iing Instrumentation (ICCI) Commit-Iments (SSER 6 II.F.2)

I Control rod position Prior to initial I Instrumentation is installed criticality limmediately after fuel load, prior Ito initial criticality B 1 Core exit temperature Prior to 5X power I B 1 Coolant level in reactor Prior to 5X power I B 3 RCS solub. Boron Conc. (0-6000) I Prior to 5% power IPost Accident Sampling System l(ANPP-33573)

C Radioactive concentration or radiation level Prior to initial INo activity in reactor'coolant in circulating primary coolant criticality Isystem prior to initial criticalityl 3 Analysis of 'primary coolant Prior to 5% power ICapability provided by PVNGS Grab II ISample PASS (ANPP-33573)

C 3 Containment area radiation monitors Prior to Mode 4 ISee Footnotes (1) and (2)

I c 3 . Effluent radioactivity-noble gas effluent Prior to Mode 4 ISee Footnotes (1) and (2)

I I from condenser air removal system exhaust I I I c I 2 Containment effluent radioactivity-noble Prior to Mode 4* I See Footnote (1)

I gases from identified release points I I C 2 Radiation exposure rate Prior to initial INo activity prior to initial I I I criticality Icriticality I c I 2 Effluent radioactivity-noble gases from Prior to Mode 4* ISee Footnotes (1) and (2)

I I buildings I I

E I Containment area radiation Prior to Mode 4 ISee Footnotes (1) and (2)

I E I 2 Radiation exposure rate Prior to initial INo activity prior to initial I I I I criticality Icriticality E I 2 Auxiliary building airborn radioactivity Prior to Mode 4* ISee Footnotes (1) and (2) I I E I 2 Condenser air removal system exhaust I Prior to Mode 4 ISee Footnotes (1) and (2)

E I 2 Common plant vent discharge any of above Prior to Mode 4* ISee Footnote (1)

I I I

• Two of these monitors are required by fuel load per the Tech. Specs. and they will be done by fuel load. We are taking no exceptions to the Tech. Specs.

'I t I ~. ~

II k ~

t I 1 1

1 1

I t 1 I

,I H

I II 1

'I il I

I HI It tl I

th II t ti 1

ht 1

1 I

1 II 1

d f I'

p ~

I jl t 1 I

1 C t 1 f

I~

~H I 4 I

1 t

~ 1 tp Il II

f. ~

I t

I 1 ' t 1'

I It 1

1 II t N it d

It I

I 4

ATTACHMENT 3

'(Continued)

CATE-,

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

1 4

h i 44 I

4 I'