ML20138E415

Requests That PM for Each CE Plant Review Licensee Response to GL 89-19 to Ensure That 901031 Submittal Applicable to Plant & That Licensee Response Addressed Operator Training Procedures.Ser,Sample Closeout & Sample RAI Ltrs Encl

ML20138E415
Person / Time
Site:	Saint Lucie, Palo Verde
Issue date:	09/07/1994
From:	Jabbour K Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20136C539	List: IR 05000335/1994009 IR 05000335/1996002 L-96-227, Forwards LER 96-S01 Re Tampering W/Key Switches on Hot Shutdown Control Panels ML20136D791 ML20136D826 ML20136E630 ML20136F193 ML20136F567 ML20136F583 ML20136G294 ML20137D421 ML20137D508 ML20137D737 ML20137D744 ML20138E042 ML20138E053 ML20138E195 ML20138E272 ML20138E355 ML20138E360 ML20138E409 ML20138E415 ML20138E422 ML20138E494 ML20138E500 ML20138E569 ML20138E635 ML20138E692 ML20138E708 ML20138E737 ML20138E766 ML20138E807 ML20138E836 ML20138E843 ML20138E879 ML20138E923 ML20138E937 ML20138F111 ML20138F363 ML20138F370
References
FOIA-96-485, REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR GL-89-19, NUDOCS 9409120198
Download: ML20138E415 (2)

Text

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UNITED STATES y

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NUCLEAR REGULATORY COMMISSION 4

2 WASHINGTON, D.C. 2006dMlo01

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September 7, 1994 MEMORANDUM TO:

All NRR Project Directors and CE Project Managers THRU:

Herbert N. Berkow, Director t

eff Project Directorate II-3 a

Division of Reactor Projects - I/II R

Office of Nuclear Reactor Regulatic FROM:

ab PM for USI A-47 Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

SUBJECT:

CLOSE00T, FOR COMBUSTION ENGINEERING PLANTS (EXCEPT PALO VERDE AND ST. LUCIE), OF GENERIC LETTER 89-19, MPA B-113,

" REQUEST FOR ACTION RELATED TO RESOLUTION OF UNRESOLVED SAFETY ISSUE A-47 ' SAFETY IMPLICATION OF CONTROL SYSTEMS IN LWR NUCLEAR POWER PLANTS' PURSUANT TO 10 CFR 50.54(f)"

3 By electronic mail (J. Conran, CRGR, to B. Boger, NRR), dated September 1, 1994, the Committee to Review Generic Requirements (CRGR) endorsed a relaxation, for Combustion Engineering (CE) plants, regarding the need for a steam generator (SG) overfill protection system, as recommended in Generic Letter (GL) 89-19. This relaxation is discussed in the safety evaluation report (SER) provided as Attachment 1.

The conditions that have to be satisfied for this relaxation are summarized in the following paragraph.

As a result of NRC staff review of the October 31, 1990, CE Owners Group (CE0G) response to GL 89-19, the staff concluded that if the licensee for each CE plant had: (1) implemented the appropriate operator training and procedures to address SG overfill events and small-break LOCA scenarios, and (2) performed an evaluation to confirm the applicability of the CEOG analyses to its plant, then the autonatic overfill protection system is not necessary, and the plant meets the recommendations of the GL. The staff's findings and conclusions are documented in the attached SER.

Based on the above conclusion for the CE plants, we request that the PM for each CE plant (except Palo Verde and St. Lucie) review their licensee's response to GL 89-19 to ensure that the October 31, 1990, submittal is applicable to their plant, and that the licensee's response addressed operator training and procedures.

If the PM's review of the licensee's response confirms that the submittal satisfactorily addressed the above conditions (i.e., applicability of the generic analyses to the facility, and operator training and procedures that address SG overfill and small-break LOCAs), then the PM should send a letter to the licensee closing out this issue. A sample

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O d,, closeout letter is included as Attachment 2.

However, if the review shows that the licensee did not satisfactorily address the conditions mentioned above, then the PM should request the licensee to provide the missing information or justify its position. A sample letter is included as.

Please include J. Wermiel, Branch Chief, Instrumentation and Controls Branch, on concurrence, and add K. Jabbour and S. Rhow on distribution for all correspondence to the licensee on this issue.

If you have any questions or require assistance, please contact the lead technical reviewer, Sang Rhow, at 504-2826, or the lead Project Manager, j

Kahtan Jabbour, at 504-1496. This memorandum and Attachments 2 and 3 are on the LAN (Filename: S:\\CLOFORCE.CRG).

Attachments-l.

Safety Evaluation Report 2.

Sample Closecut Letter 3.

Sample RAI Letter l

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