NRC Generic Letter 1986-17
| ML031150302 | |
| Person / Time | |
|---|---|
| Issue date: | 10/17/1986 |
| From: | Bernero R Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| GL-86-017, NUDOCS 8610230062 | |
| Download: ML031150302 (5) | |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555 OCTi?18 TO ALL LICENSEES OF BOILING WATER REACTORS AND APPLICANTS
Gentlemen:
SUBJECT: AVAILABILITY OF NUREG-1169, "TECHNICAL FINDINGS RELATED TO
GENERIC ISSUE C-8; BOILING WATER REACTOR MAIN STEAM ISOLATION
VALVE LEAKAGE AND LEAKAGE TREATMENT METHODS" (Generic Letter 86-17)
This letter is to inform you that NUREG-1169, "Technical Findings Related to Generic Issue C-8; Boiling Water Reactor Main Steam Isolation Valve Leakage and Leakage Treatment Methods", was published in June, 1986. This NUREG
presents the results of the NRC staff and contractor efforts to assess Generic Issue C-8, "MSIV Leakage and LCS Failures". This issue deals with the difficulty of some main steam isolation valves (MSIVs) in Boiling Water Reactors (BWRs) to meet Technical Specification leakage rate limits (which are typically 11.5 SCFH at a 25 psig test pressure) and with the need for leakage control systems. The leakage rates are based on a large loss-of-coolant accident (LOCA), a specified design basis source term from the core (TID 14844),
the worst single active failure, and no credit for any non-seismic Category I
equipment, components, and structures. To ensure acceptable performance guidelines for engineered safety features, leakage control systems (LCS) have been installed on most BWRs to direct any leakage past MSIVs during the design basis LOCA to an area served by the Standby Gas Treatment System (SGTS). If the leakage rate past an MSIV significantly exceeds the Technical Specification value, the LCS may not be effective because of limitations in its design.
As a result of these concerns, the staff prioritized the MSIV leakage and LCS
failures as a high priority Generic Issue in January 1983. Independently, the BWR Owners Group (BWROG) formed the MSIV Leakage Control Committee to determine the cause of high leakage rates associated with many of the MSIVs, and to develop recommendations for reducing the leakage rates. The BWROG
-: Committee completed its effort and provided recommendations and comments to the staff in February, 1984 and April, 1986.
In evaluating MSIV leakage with respect to offsite'doses following a LOCA, the technical evaluation of this Generic Issue has used realistic assumptions concerning the equipment, facilities and site characteristics available to mitigate the effects of a LOCA. The specific elements of the effort were:
° To evaluate the BWROG recommendations associated with reducing leakage past the MSIVs and assess the effectiveness of the recommendations as implemented by licensees.
o To evaluate the existing safety-related LCS comparing it's effectiveness with that of other methods of handling the leakage likely to be available following a LOCA.
A4,
DOT 1 7 1986 o To perform a probabilistic risk assessment (PRA) to evaluate the reliability and relative risks associated with the different methods of mitigating the effects of a LOCA.
° To evaluate the use of alternate equipment to mitigate the effects of a LOCA, and potential changes in allowable MSIV leakage rates.
o To identify areas in current licensing guidance (the Regulations, the
- Standard Review Plan, the Regulatory Guides, and the Technical Specifications) that are related to MSIVs and LCSs that will be considered inthe second, or regulatory assessment, phase of resolution.
of the generic issue.
A safety-related LCS was evaluated by comparing it's effectiveness with other methods of handling leakage that could be available following a LOCA. Several ways to treat leakage which make.-use of the holdup volume and surfaces of the main steam lines (MSL) and condenser and fission product attenuation elsewhere, were considered. A PRA considering the reliability and relative risks associated with the different-methods of mitigating the effects of a LOCA was performed.
The overall risks from the accident sequences inwhich MSYV leakage could be a significant factor were found to be low without an LCS, and alternate fission product handling techniques were shown to produce significant potential dose reductions.
NUREG-1169 represents technical findings associated with Generic Issue C-8 and the staff expects it tlobe used in the regulatory resolution of the issue. The latter is anticipated to be complete inanother year incoordination with ongoing generic activities relating to accident source terms, to overall containment leak rate and leak rate testing considerations.
Neither this letter nor NUREG-1169 constitute a change inthe existing generic staff positions or allowable MSIV leakage rates, nor the specifications for MSIV leakage control systems. Therefore, no action is being requested of applicants or licensees. The information contained in NUREG-1169, however, including the recommendations of the BWROG, may be useful guidance for some licensees contemplating plant specific change requests related to this issue pending final generic resolution.
NUREG-1169 may be purchased by calling (202) 275-2060 or (202) 275-2171 or by writing to the Superintendent of Documents, U.S. Government Printing Office, Post Office Box Number 37082, Washington, D. C. 20013, or the National Technical Information Service, Department of Commerce, 5258 Port Royal Road, Springfield, Virginia 22161. I
GOT 17a
-3- This letter is provided for information only. It does not contain any new requirements or guidance for licensees of boiling water reactors. Actions based on the contents provided herein are voluntary and no reply to the NRC is required.
Sincerely, Acb~ertXb r Robert M. Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation OFC : PSB:DBL PSB:DBL A:R
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OFFICIAL RECORD COPY
LIST L. RECENTLY ISSUED GENERIC L TERS
Generic Date of Letter No. Subject Issuance Issued To GL 86-16 WESTINGHOUSE ECCS EVALUATION 10/22/86 ALL
MODELS PRESSURIZED
WATER REACTOR
APPLICANTS AND
LICENSEES
6L 86-15 INFORMATION RELATING TO 09/22/86 ALL LICENSEES
COMPLIANCE WITH 10 CFR 50.49, AND HOLDERS OF
"EQ OF ELECTRICAL EQUIPMENT AN APPLICATION
IMPORTANT TO SAFETY" FOR AN
OPERATING
LICENSE
6L 86-14 OPERATOR LICENSING 08/20/86 ALL POWER
EXAMINATIONS REACTOR
LICENSEES AND
APPLICANTS
GL 66-13 POTENTIAL INCONSISTENCY 07/23/86 ALL POWER
BETWEEN PLANT SAFETY ANALYSES REACTOR
AND TECHNICAL SPECIFICATIONS LICENSEES WITH
PRESSURIZED
WATER REACTORS
OL 86-12 CRITERIA FOR UNIQUE
PURPOSE
07/03/66 ALL NON-POWER
EXEMPTION FROM CONVERSION FROM REACTOR
THE USE OF HEU FUEL LICENSEES
AUTHORIZED TO
USE HEU FUEL
GL 66-11 DISTRIBUTION OF PRODUCTS 06/25/86 ALL NON- POWER
IRRADIATED IN RESEARCH REACTOR
REACTORS LICENSEES
6L 66-10 IMPLEMENTATION OF FIRE 04/28/86 ALL POWER
PROTECTION REQUIREMENTS REACTOR
LICENSEE AND
APPLICANTS
6L 86-09 TECHNICAL RESOLUTION OF 03/31/86 ALL BWR AND
GENERIC ISSUE NO. B-59 PWR LICENSEES
(N-1) LOOP OPERATION IN BWRS AND APPLICANTS
AND PWRS
GL 86-08 AVAILABILITY OF SUPPLEMENT 4 03/25/86 ALL LICENSEES,
TO NUREG-0933, "A APPLICANTS AND
PRIORITIZATION OF GENERIC CONSTRUCTION
SAFETY ISSUES" PERMIT HOLDERS
GL B6-07 TRANSMITTAL OF NUREG-1190 03/20/86 ALL LICENSEES
REGARDING THE SAN ONOFRE UNIT AND APPLICANTS
1 LOSS OF POWER AND WATER
HAMMER EVENT
iCT I7 c
- 3 -
This letter is provided for information only. It does not contain any new requirements or guidance for licensees of boiling water reactors. Actions based on the contents provided herein are voluntary and no reply to the NRC is required.
Sincerely, Robert M. Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation OFC : PSB:DBL PSB:DBL Ae WR
- KA D:SRO D:BWR
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NAME :JRidgely:ye : iman :G nas : TSpeis : RBer ero :
DATE :01S1t/86 :1IG3 /86 :10/ /86 :10/ /86 :19/rI /86 OFFICIAL RECORD COPY