ML20093C270

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Responds to NRC & SER on BWR Owners Group Response to NUREG-0737,Item II.K.3.16 Re Reduction of Challenges & Failures of Relief Valves - Feasibility Study & Sys Mod.Acceptable Mods & Util Responses Listed
ML20093C270
Person / Time
Site: Oyster Creek
Issue date: 10/03/1984
From: Fiedler P
GENERAL PUBLIC UTILITIES CORP.
To: Paulson W
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.16, TASK-TM NUDOCS 8410100454
Download: ML20093C270 (2)


Text

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GPU Nuclear Corporation NQgIgf Post Office Box 388 Route 9 Soutn Forked River.New Jersey 08731-0388 i

609 971-4000 9

Writer's Direct Dial Number:

October 3, 1984 Mr. Walter A. Paulson, Acting Chief Operating Reactors Branch #5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Paulson:

Subject:

Dyster Creek Nuclear Generating Station Docket No. 50-219 NUREG-0737, Item II.K.3.16 Ref (1): NED0-24951, Chapter 6 - Reduction of Challenges and Failures of Relief Valves Per NUREG 0737 Requirement II.K. 3.16 (2): NRC letter dated April 11, 1984 with Safety Evaluation Report "BWR Owner's Group Response to Item II.K.3.16 of NUREG 0737, ' Reduction of Challenges and Failures of Relief Valves-Feasibility Study and System Modification The purpose of this letter is to respond to your letter (reference 2 above) dated April ll,1984. This letter described methods acceptable to the NRC in order to reduce SRV challenges and ' allures. Listed below are the acceptable modifications and our response:

(1 ) Low-Low Set Relief Logic System or Equivalent Manual Actions; RESPONSE - For a BWR/2 with Dresser valves, this modification has no effect on S0RY Event Frequency or S/RV Challenges per tables 5.1 and 5.2 of Reference (1). GPUN has not implemented this and has no plans to implement this in the future.

(2) Lower the reactor pressure vessel water level isolation setpoint for main steam isolation valve closure from Level 2 to Level 1; RESPONSE - This modification is not applicable to Oyster Creek per Reference (2)

"This system modification is not applicable to BWR/2-3 because the level instrumentation design for these plants is incompatible with the design described herein".

(3) Increase safety / relief valve simmer margin; RESPONSE - This modification is not applicable to Oyster Creek as it j

applies to Target Rock three stage valves.

hD 8410100454 841003

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PDR ADOCK 05000219 P

PDR t O.

GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

  • Walter A. Pauls n, Acting Chief U.S., Nuclear R:gulat:ry Comission Page 2~

(4) ' Preventative Maintenance Program; RESPONSE.- This is applicable to Oyster Creek. GPUN is implementing a preventative maintenance program for the Dresser electromatic relief valve which requires that all 5 valves be tested and refurbished each outage. All 5 valves were tested and refurbished during our current outage.

'In addition to the above, it was requested that we respond to the following questions:

. (1) Which, if any of the staff recomended modifications have been

implemented?

RESPONSE - Recoisnendation (4), Preventative Maintenance Program, has been implemented at Oyster Creek.

(2) Which, if any, of the staff recomended modifications do you propose to implement?

RESPONSE - GPUN does not propose to implement any of the staff recommended modifications other than preventative maintenance.

(3) Whether you have implemented or propose to implement any of the other modifications or actions discussed in NUREG-0737, Item II.K.3.16 or in the BWR Owners Group report.

RESPONSE - In response to these questions, we note that Tables 5.1 and 5.2 of Reference (2) show no signifcant effect on SORY Event Frequency or S/RY Challenges for a BWR/2 with Dresser valves for the candidate modifications.

Therefore, GPUN has no plans to implement any other modifications..

Should you require any further infonnation on this subject, please contact Mr. Michael Laggart, BWR Licensing Manager at (201) 299-2341.

Very truly yours,

,A AAb

. Fiedler Vice President and Director Oyster Creek PBF/ dam cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station

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Forked River, 'NJ - 08731 l'

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