ML17298B341

Forwards Proposed Change to Section 1.8 of FSAR Re Exception to ANSI N18.17 Endorsed by Reg Guide 1.17.Change Made to Provide Consistency Between FSAR & Security Plan

ML17298B341
Person / Time
Site:	Palo Verde
Issue date:	10/15/1984
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Knighton G Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.017, RTR-REGGD-1.017 ANPP-30843-TFQ, NUDOCS 8410170033
Download: ML17298B341 (10)

Text

REGULATORr INFORMATION DISTRIBUTION 6 STEM (RIDS)

ACCESSION NBR 8410170033 DOC ~ DATE 8P/10/15 NOTARIZED YES DOCKET FACIL-STN '50"528 Palo Verde Nuclear Stationi Unit li Arizona Publ i STN 50-529 Palo Verde Nuclear Statiani Unit 2i Arizona Publi 050 0

29 STN-50-530 Palo Verde Nuclear Stations Unit 3~ Arizona Publi 05000530 AUTH',NAME AUTHOR AFFILIATION VAN BRUNTiE ~EArj zona Pub l j c Service Co ~

RECIP,NAME.

RECIPIENT AFFILIATION KNIGHTONgG ~

Licensing Branch 3

SUBJECT:

Forwards proposed change to Section 1 '

of FSAR re exception to ANSI N18,17 endor sed by Reg Guide 1 ~ 17,Change made to provide consistency between FSAR 8 security plan, DISTRIBUTION CODE:

B001D COPIES RECEIVED:LTR ENCL SIZEt TITLE: Licensing Submittal:

PSAR/FSAR Amdts 8, Related Correspondence NOTES:Standardized

plant, Standardized plant ~

Standardized plant ~

05000528 05000529 05000530 RECIPIENT ID CODE/NAME NRR/DL/ADL NRR LB3 LA COPIES RECIPIENT LTTR ENCL ID CODE/NAME 1

0 NRR LB3 BC 1

0 LICITRAiE 01 COPIES LTTR ENCL 1

0 1

1 INTERNALS ADM/LFMB IE FILE IE/DEPER/IRB 35 NRR ROEgM,L NRR/DE/CEB 11 NRR/DE/EQB 13.

NRR/DE/MEB 18 NRR/DE/SAB 2Q NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DSI/AEB 26 NRR/DS I/CPS 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DSI/RSB 23 RGN5 EXTERNAL: ACRS 01 DMB/DSS (AMDTS)

LPDR 05 NSIC 05 1

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1 1

1 1

1 1

2 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 3

6 6

1 1

1 1

1 1

ELD/HDS3 IE/DEPER/EPB 36 IE/DQASIP/QAB21 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/AS8 NRR/DSI/CSB 09 NRR/DSI/METB 12 NR

/RAB 22 0Q RM/DDAMI /MIB BNL(AMDTS ONLY)

FEMA REP DIV 39 NRC PDR 02 NTIS 1

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1 1

1 1

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1 0

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LTTR 55 ENCL 47

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Arizona Public Service Company Director of Nuclear Reactor Regulation Attention: Mr. George Knighton, Chief Licensing Branch No. 3 Division of Licensing U. S. Nuclear REgulatory Commission Washington, D. C. 20555 October 15, 1984 ANPP-30843 TFQ/JYM

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3

Docket Nos. STN-50-528/529/530 Exception to R.

G. 1.17 File: 84-056-026.

G.1.01.10

Dear Mr. Knighton:

Attached is a proposed change to Section 1.8 of the FSAR concerning an exception to ANSI N18.17 which is endorsed by Regulatory Guide 1.17.

The change was made to provide consistency between the FSAR and the Security Plan.

If you have any questions on this matter, please contact me.

Very truly yours, EEVBJr/JYM/bg Attachment E. E.

Van Brunt, Jr.

APS Vice President Nuclear Production ANPP Project Director no~

ceo E. A. Licitra w/a A. C. Gehr w/a 84i0i70033 84iOi5 PDR ADOCK 05000528~,

F PDR L

0

ANPP-30843 STATE OF ARIZONA

)

) san COUNTY OF MARICOPA)

I, Edwin E.

Van Brunt, Jr.,

represent that I am Vice President, Nuclear Production of Arizona Public Service

Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, that I have read such document and know its

contents, and that to the best of my knowledge and belief, the statements made therein are true.

Edwin E.

Van Brunt, Jr.

Swo-m ro 'Lafore me thief~day of

, 1984.

ae S

e' Hy Commissiol'; Expires:

M}fCGAiFi',csI",I1 F~',pj~", /'",;,.

(;

)<

Notary Public hf

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PVNGS FSAR SPIEE T ~ D< ~8 CONFORMANCE TO NRC REGULATORY GUIDES REGULATORY GUIDE 1.17:

Protection of Nuclear Power Plants Against Industrial Sabotage (Revision 1, June 1973)

RESPONSE

~ ~

The position of Regulato'ry Guide 1.17 is accepted with the following exceptionsf+> Al4SX'8-l7- / 5

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sc r aequi liP.

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corted access to protected and vital areas (excluding

. sensiti e I" areas) may be authorized where an in 'aual has a.current cer 'cation by his employer or' eithe

.1.

to have been in the em er's.c z.nuous e'mployment for at least 2 years wit e 'nce adversely reflecting on the oyee's reliabi'r trust-

. worthiness, 2.

to e satisfactorily completed the general scree~.'ng program.

. Unescorted access to sensitive (Type I Vital) areas may be authorized where an individual has a current certification by his employer or PVNGS either:

to have been in the employer's continuous employment'or at least 3 years without evidence adversely reflect-

'ng on the employee's re ab'lit<< or trustworthiness, or 2.

to have satisfactorily completed the ensitive (Type Vital} area screening program.

T eriods specified in subparagraphs (1) and (2

be reduced to

.m emolovees o

tractors who are e

>g p

~

outages, pz hat physical 1.8-8

\\

I

~1

~"

(-

Insert 1 to Exceptions to R.

G. 1.17 As a temporary measure, interim clearances for Unescorted Access may be granted for a period not to exceed 90 dmys.

Unescorted Access to the Protected Area and occupied Type II Vital Areas shall require a

positive identification check (drivers license or comparable means) and a telephone or written check of trustworthy employment in the previous 12 month period.

Temporary Unescorted Access to Type I Vital Areas shall require the previously mentioned checks of positive identifi-cation and trustworthy employment, and the institution of a two-man rule (buddy system).

I

~

~

PVNGS FSAR SffcF'-7 + ~+

CONFORMANCE TO NRC REGULATORY G>>IDES in ections of plant and equipment to which these personn ll have ha escorted access are performed upon complet' of the outage.

"Physical inspection --

s a visual ins ction by Operations I

personnel to observe that no eqi misalignment has been made to vital equipment locat xn" th ffected area."

The physical inspec 'ay be combined with operability test require y technical specifications.

Re to section 13.6.2.

REGUf ATORY GUIDE l. 18:

Structural Acceptance Test for Concret..

Primary Reactor Containments (Revision 1, December 28, 1972)

RESPONSE

Regulatory Guide 1.18 established-a.systematic approach to testing wherein quantitative information is obtained concern-ing structural response to pressurization.

The following interpretations of the Regulatory Guide are provided:

A.

Position C.2 of the Regulatory Guide The numb r and distribution of measuring points for monitoring radial deflection is.selected so that, the as-built condition can be considered in the assessment of roundup, bu"tres -she"1 interaction, and general shell esporse.

';.ieasuremen",.s ar mad at points simil=.r to those shown in chapter 9 of BC-TOP-5-A.

However, obtain the most significant data, the measuring point locations may be changed to those where the as-built containment is at the limit of'tolerances if such points, exist.

Accordingly, an arbitrary selection of measurement points is not intended.

October 1981 Amendment 6