ML20205K749
| ML20205K749 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Beaver Valley |
| Issue date: | 02/20/1986 |
| From: | Stello V NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | Fraley R Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML20205D576 | List: |
| References | |
| FOIA-86-126, FOIA-86-127, FOIA-86-131, FOIA-86-166, FOIA-86-201, FOIA-86-209, FOIA-86-263, FOIA-86-80, FOIA-86-82 NUDOCS 8602280794 | |
| Download: ML20205K749 (3) | |
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BISTRIBUTION:
C:ntral Flics JRoe GCunningham JFunches LRubenstein TOSB R/F TRehm HDenton CTaylor JLyons VStello JHeltemes DEisenhut RMinogue RHernan JSniezek EDO R/F FEB 2 01986 BSheron NRR Division Directors ra" MEMORANDUM FOR: Raymond F. Fraley, Executive Director gm D
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Advisory Committee on Reactor Safeguards FROM:
Victor Stello, Jr.
Acting Executive Director for Operations
SUBJECT:
307th ACRS MEETING (N0VEMBER 7-9,1985) FOLLOW-UP ITEMS
REFERENCE:
Memo from R. Fraley to W. Dircks, subject as above, dated November 25, 1985 The following information is provided in response to those specific items in the referenced memorandum that pertain to the Office of Nuclear Reactor Regulation.
1.
ACRS Report on Beaver Valley Power Station, Unit 2 The staff is preparing a Supplement to the Beaver Valley Unit 2 Safety Evaluation Report (SER) which will specifically address the issues raised in the November 13, 1985 ACRS report. This supplement is scheduled for issuance in March 1986. The current estimate of construction completion for this plant is April 1987.
i In response to the steam generator overfill issue, a number of actions l
have been completed or are in progress. The staff identified the need for more information on steam generator tube rupture (SGTR) as a confirmatory item in the Beaver Valley SER. The Beaver Valley Unit 2 FSAR contains an analysis for system response and radiological con-sequences of SGTR which assumes. leak termination in 30 minutes. The staff requested the applicant to justify this time period.
In response, the applicant stated that the Westinghouse Owners Group is investigating several SGTR licen ing concerns and will address the staff's concerns l
0 through generic evaluations. When this additional information is received, the staff will complete its review of this confirmatory item and report the results of the review in a supplement to the SER.
The Beaver Valley SER (Section 7.3.3.12) discusses steam generator level control and protection as a backfit issue.
In accordance with the staff's plant-specific backfit procedure, a backfit appeal meeting was requested by the applicant. This meeting was held on May 9, 1985 with the Director, Division of Licensing. As stated in the SER, a conclusion was reached that, if the applicant did not make hardware modifications to the steam generator level control system, there was no undue risk to the public health and safety for the interim period it will take to Y
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resolve USI A-47 (" Safety Implications of Control Systems"). The applicant will be required to meet any requirements that evolve from the resolution of USI A-47 to allay steam generator overfill concerns.
On a generic basis the staff is initiating a separate generic safety issue on causes of steam generator overfill other than instrument and control system failures.
In conjunction with the staff's effort, the Westinghouse Owners Group has submitted Topical Report WCAP-10698 "SGTR Analysis Methodology to Determine the Margin to Steam Generator Overfill". This document predicts the margin to overfill for various models of steam generators assuming occurrence of the design basis SGTR.
The necessary operator actions were considered and the report states that operator action times were based partially on simulator runs. The analysis assumed a concurrent loss of offsite power and sensitivity analyses were performed to determine the effects of a spectrum of single active failures. The staff has performed a preliminary review of this analysis, which indicates that the methodology is reasonable but that the assumed operator action times appear optimistic. The WOG plans to submit a supplement to this report which will deal with the i
consequences of overfill, including steam line dynamic load analyses,
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the effects on the operability of secondary safety valves and the con-l sequences of safety valve failures. Upon receipt of this document I
(tentatively scheduled for February 1986) the staff will initiate a detailed review of WCAP-10698 and the overfill supplement. Satisfactory resolution of the generic steam generator overfill problem for l
Westinghouse plants and acceptable results for the offsite radiological consequence analyses would satisfy the staff's concerns regarding the effects of overfill as a result of SGTR. As far as other causes of overfill, the staff has included an assessment of instrument failures as a potential cause of steam generator overfill as part of USI A-47.
The ACRS report states that the Committee wishes to be briefed on the application of leak-before-break criteria to certain Beaver Valley Unit 2 balance-of-plant piping systems "before implementation".
Implementation of the engineering and design aspects of this program had already begun at the time of the 307th ACRS meeting and will be a continuing effort up until the time of plant completion. The staff plans to meet with the licensee at least quarterly to discuss the i
status of this program as it develops.
Implementation as applied to actual construction would be in the form of not installing certain l
pipe whip restraints and jet impingement barriers presently required by NRC regulations. Therefore, before an operating license can be i
issued, the staff must either change the regulations via rulemaking or grant an exemption to portions of this regulation. The staff is in the process of proposing a broad scope change to 10 CFR 50 Part A, General j
Design Criteria No. 4 to allow application of leak-before-break t chnology
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e to piping systems under certain conditions. This proposed rule was discussed with the CRGR on January 22, 1986 and will be discussed with the ACRS Metal Components Subcommittee on February 27-28, 1986.
Briefings of the ACRS on the Beaver Valley Unit 2 program will be scheduled, as appropriate, prior to licensing the plant.
Origina1 signed b7 Victor Stello Victor Stello, Jr.
Acting Executive Director for Operations f
4 PD/DPL/A*
- See Previous Concurrence LRUBENSTEIN Revised by OED0 2/18/86 2/12/86 0FC :TOSB:PPAS*
- TOSB:PPAS* : DIR:PPAS* : DDIR:NRR* : DIR:NRR*
DDIR/DSR0*:E00 NAME :RHERNAN:no : JLYONS
- JFUNCHES
- DEISENHUT : HRDENTON
- BSHERON
- VSTRLO DATE :1/28/86
- 1/28/86
- 1/28/86
- 1/28/86
- 2/13/86 2/12/86
- 2//
0FFICIAL RECORD COPY
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