ML17300A798

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Reconfirms That Unit 1 Post Accident Sampling Sys (PASS) Meets or Exceeds Requirements Established by NUREG-0737, II.B.3.FSAR Will Be Updated to Reflect Differences Between Unit 1 & Units 2 & 3 Pass.Fee Paid
ML17300A798
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 04/24/1987
From: Haynes J
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM 161-00170-JGH-D, 161-170-JGH-D, NUDOCS 8705070014
Download: ML17300A798 (6)


Text

REGULATOR NFORMATION DISTRIBUTION: TEN (R IDS)

ACCESSION NBR: 87050700 i4 DOC. DATE: 87/04/24 NOTARIZED: NO FACIL:STN-50-528 Palo Verde Nuclear Station~ Unit li Av izona Publi STN-50-529 Palo Vev'de Nuclear Stations Unit 2> Arizona Pub BTN-50-530 Palo Verde Nuclear Station> Unit 3i Arizona Publi li AUTH. NAME AUTHOR AFFILIATION HAYNES> S. Q. Av'i zona. Nuc leav Pouev Pro Ject ( formev lg Av i zona Pub 1 ic Serv REC IP. NAME RECIPIENT AFFILIATION Document Control Franch (Document Contv ol Desk)

SUBJECT:

Pv'oposes mods to Unit i intev im post accident sampling sos be v'educed on basis oF ALARA concern. Nods decribed in util 850926 ltr to be completed priov to v estart of. Unit i v eFueling outage. Fee paid.

DISTRIBUTION CODE. AOOID TITLE: OR COPIEB RECEIVED: LTR Submittal: Qeneval Distv ibution I ENCL 0 SIZE:

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TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL

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Arizona Nuclear Power Project P.O. SOX 52034 ~ PHOENIX, ARIZONA85072-2034 April 24, 1987 161-00170-JGH/DAL U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3 Docket Nos. STN 50-528 (License NPF-41)

STN 50-529 (License NPF-51)

STN 50-530 (License NPF-65)

Post Accident Sampling System (PASS)

File: 87-009-545; 87-056-026

Reference:

(1) Letter to G. W. Knighton, (NRC) from E. E. Van Brunt, Jr.,

ANPP dated September 26, 1985 (ANPP-33573).

Subject:

Post Accident Sampling System.

(2) Letter to J. B. Martin, (USNRC Region V) from E. E. Van Brunt, Jr., ANPP, dated August 19, 1985 (ANPP-33238).

Subject:

Post Accident Sampling Program.

Dear Sir:

Reference (1) transmitted changes to the PVNGS Final Safet Anal sis Re ort (FSAR) and Lessons Learned Im lementation Re ort LLIR which describe the PVNGS grab sample type post accident sampling system. Reference (1) also stated the PVNGS Unit 1 interim PASS would be upgraded in accordance with the changed FSAR description prior to restart following the first refueling.

On the basis of an As Low As Reasonably Achievable (ALARA) concern, ANPP proposes that modifications to the Unit 1 interim PASS, as described in Reference (1), be reduced.

ALARA Group reviews of the Unit 1 PASS upgrade work show that undesirable personnel radiation exposure will be required to install the Reference (1)

PASS modifications. This radiological hazard has been created by plateout of cobalt and antimony in the Unit 1 shutdown cooling system. The plateout has created unshielded dose rates in the PASS work areas which vary from 50 mr/hr to 1000 mr/hr. Shielding is projected to lower dose rates to 20-50 mr/hr.

Since a minimum estimated 6,050 man-hours would be required to remove old equipment and install and test new equipment, a minimum of 180 man-rem would be experienced. Required operation of the shutdown cooling system could result in increased exposure up to 600 man-rem.

8705070014 870424 PDR ADDCK 05000528 p PDR

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U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Page Two ANPP reconfirms the Unit 1 PASS meets or exceeds the requirements established by NUREG-0737, II.B.3, as stated in Reference (2). ANPP will modify the Unit 1 interim PASS to provide the capability to sample the auxiliary building sump in accordance with Regulatory Guide 1.97, Revision 2. Th'is modification will be completed prior to restart following completion of the Unit 1 first refueling outage. The FSAR will be updated to reflect the differences between the PVNGS Unit 1 PASS and the PVNGS Units 2 and 3 PASS.

Work is currently in progress to assure installation of modifications outlined in Reference (1), prior to restart following completion of the Unit 1 first refueling outage. Expeditious approval of this proposal is requested to reduce radiation exposure to plant personnel. In accordance with 10CFR 170.12(c), the approval request fee of 4150 has been forwarded to the USNRC Fee Management Coordinator.

Please contact me if you have any questions or require further information on this matter.

Very truly yours, J. G. Hay es Vice President Nuclear Production JGH/DAL/)le cc: 0. M. De Michele E. E. Van Brunt, Jr.

G. W. Knighton E. A. Licitra J. B. Martin G. P. Yuhas H. S. North R. P. Zimmerman R. M. Diggs (with WFD $ 150)