ML17312A860

Forwards Response to NRC Bulletin 96-002, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core or Safety-Related Equipment.

ML17312A860
Person / Time
Site:	Palo Verde
Issue date:	07/16/1996
From:	Stewart W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
102-03733-WLS-A, 102-3733-WLS-A, IEB-96-002, IEB-96-2, NUDOCS 9607220272
Download: ML17312A860 (14)

Text

CATEGORY 3~

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9607220272 DOC.DATE: 96/07/16 NOTARIZED: YES DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH. NAME AUTHOR AFFILIATION STEWART,W.L. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Contr'ol Desk)

SUBJECT:

Forwards response to NRC Bulletin 96-002, "Movement of Heavy Loads Over Spent Fuel, Over Fuel in Reactor Core or Safety-Related Equipment."

DISTRIBUTION CODE: IE11D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Bulletin Response (50 DKT)

NOTES:STANDARDIZED PLANT 05000528 8 Standardized plant. 05000529 Standardized plant. 05000530 0 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 PD 1 1 CLIFFORDIJ 1 1 CLIFFORD,J. 1 1 INTERNA FiLE CENTE~ 1 1 NRR/DE/EMEB 1 1 RR/DRPMjjPECB 1 1 NRR/DSSA 1 -1 NRR/DSSA/SCSB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SPLB/A 1 1 NRR/DSSA/SRXB 1 1 D NRR/PD3-2 1 1 NUDOCS-ABSTRACT 1 1 RES/DSIR/EIB 1 1 RGN4 FILE 01 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 U

E N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 17

4i Ci Arizona Public Service PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034 PHOENIX. ARIZONA 85072.2034 WILLLtIML STEWART 102-03733-'WLS/AKK/DR L EXECUTIVE VICE PRESIDENT NUCLEAR July 16, 1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3

-Docket-Nos. STN 50-528/529/530 Response to 'NRC Bulletin 96-02, "Movement of Heavy Loads Over Spent Fuel, Over'Fuel in the Reactor Core, or Over Safety-Related

.Equipment;".dated April 11, 1996 Enclosure 1 contains Arizona Public Service Company's.(APS) response, as. required by NRC Bulletin 96-02, concerning handling of heavy loads while at power.

APS confirms that the required review of. plans and capabilities for handling of heavy loads while the reactor is at power, is complete. The review has determined that APS is in compliance-with,its current licensing basis. APS does not plan to request-changes to its heavy load handling capability within.the next two years.

Should you have any questions, please contact Scott A. Bauer, at (602) 393-5978.

Sincerely, 44 WLS/AKK/DRL/rv

Enclosure:

cc: L. J. Callan (all w/Enclosure)

K. E. Perkins J. W. Clifford K. E. Johnston 9607220272 960716 PDR ADQCK 05000528 8 PDR

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STATE OF ARIZONA )

) s.s..

COUNTY OF MARICOPA)

I, W. L. Stewart, represent-that I am Executive Vice President - Nuclear, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with my full authority to do so, and that to the best of my knowledge and belief, the statements made herein are true and correct.

W. L. Stewart Sworn To Before Me This +I Day Of J , 1996 Notary Public My Commission Expires JUDG~2,4997 py Colmlsston

I ENCLOSURE 1 RESPONSE TO NRC BULLETIN 96-02

V In accordance with the requested action of NRC Bulletin 96-02, APS has performed a review of plans and capabilities for handling heavy loads while the reactor is at power in accordance with existing regulatory guidance.

Re uired Res onse1 Required. Response 1 states:

(1) For licensees planning to implement activities involving the handling of heavy loads over spent fuel, fuel in the reactor, core, or safety-related equipment within the next 2 years from the date of this bulletin, provide the following:

o A report, within 30 days of the date of this bulletin, that addresses the licensee's review of its plans and capabilities,to handle heavy loads while the, reactor is at power (in all modes other than cold shutdown, refueling,, and defueled) in accordance with existing regulatory guidelines. The report should also indicate whether the activities are within the licensing basis. and should include, if necessary, a schedule for submission of a license amendment request. Additionally, the. report should indicate whether changes to Technical Specifications will be required.

~Res onse NUREG-0857, "Safety Evaluation Report Related to the Operation of Palo Verde Nuclear.

Generating Station, Units 1, 2, and 3," Supplement 5, Appendix D, "Control of Heavy Loads. at Nuclear Power Plants, Palo Verde Nuclear Generating'Station, Plants Number 1, 2, an 3 (Phase I)" documents the acceptance of Palo Verde's control of heavy loads.

This included a review of the establishment of safe load paths necessary to meet the requirements of Guideline 1 of NUREG-0612, Article 5.1.1(1) as well as the method for deviating from approved load paths. Supplement 7, Section 9.1.4 to the SER documents that Phase II of NUREG-0612 did not need to be implemented.

In order to ensure continued compliance with Guideline 1 of NUREG-061 2, Article 5.1 1'(1),

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APS performed a review of plant procedures used to implement safe. load paths for heavy loads at PVNGS. The review has determined that load paths currently in use meet Guideline 1. of NUREG-0612, Article 5.1.1{1).

It is concluded. that no license amendments or Technical Specification-amendments will be required at this time.

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II Re uired Res onse 2 Required Response 2 states:

(2) For licensees planning to perform activities involving the handling of heavy loads over spent fuel, fuel in the reactor core, or safety-related equipment while the reactor is at power (in all modes other than cold shutdown, refueling, and defueled) and that involve a potential load drop accident that has not previously been evaluated in the FSAR, submit a license amendment request in advance (6-9 months) of the planned movement of the loads so as to afford the staff sufficient time to perform an appropriate review.

~Res onse At the present time, APS does not plan on performing activities involving the handling of heavy loads over the spent fuel, fuel in the reactor core, or safety-related equipment while the reactor is at power and that involve a potential load drop accident that has not been previously evaluated in the PVNGS licensing basis; i.e., the PVNGS and CESSAR SERs.

Should the need arise, APS will submit a license amendment request in advance as requested in the Bulletin, as appropriate.

Re uired Res onse 3 Required Response 3 states:

(3) For licensees planning to move dry storage casks over spent fuel, fuel in the reactor core, or safety-related equipment while the reactor is at power (in all modes other than cold shutdown, refueling, and defueled) included in item 2 above, a statement of the capability of performing the actions necessary for safe shutdown in the presence of radiological source term that may result from a breach of the dry cask, damage to the fuel, and damage to safety-related equipment as a result of a load drop inside the facility.

~Res onse PVNGS does not currently have plans for the movement of dry storage casks over spent fuel, fuel in the reacotr core, or safety-related equipment while the reactor is at power.

Appropriate evalautions will be performed, and submitted as necessary, when plans are made to utilize dry storage casks.

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Re uired Res onse 4 Required Response*4 states:

(4) For licensees planning to perform activities involving the handling of heavy

'loads over spent fuel, fuel in the reactor core, or safety-related equipment while the reactor is at power (in all modes other than cold shutdown, refueling, and defuefed), determine whether changes to Technical Specifications will be required in order, to allow the handling of heavy loads (e.g., the dry storage canister shield plug) over fuel assemblies, in the spent fuel pool and submit the appropriate information. in advance (6-9 months) of the. planned movement of the loads for NRC review and approval.

~Res ense No changes to Technical SpeciTications are required at this time.

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