NRC Generic Letter 1986-17: Difference between revisions

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| issue date = 10/17/1986
| issue date = 10/17/1986
| title = NRC Generic Letter 1986-017: Availability of NUREG-1169, Technical Findings Related to Generic Issue C-8; Boiling Water Reactor Main Steam Isolation Valve Leakage & Leakage Treatment Methods
| title = NRC Generic Letter 1986-017: Availability of NUREG-1169, Technical Findings Related to Generic Issue C-8; Boiling Water Reactor Main Steam Isolation Valve Leakage & Leakage Treatment Methods
| author name = Bernero R M
| author name = Bernero R
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 5
| page count = 5
}}
}}
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY  
{{#Wiki_filter:UNITED STATES
COMMISSION
                          NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555 OCTi?18 TO ALL LICENSEES  
                                    WASHINGTON, D. C. 20555 OCTi?18 TO ALL LICENSEES OF BOILING WATER REACTORS AND APPLICANTS
OF BOILING WATER REACTORS AND APPLICANTS
    Gentlemen:
Gentlemen:
    SUBJECT:   AVAILABILITY OF NUREG-1169, "TECHNICAL FINDINGS RELATED TO
SUBJECT: AVAILABILITY  
              GENERIC ISSUE C-8; BOILING WATER REACTOR MAIN STEAM ISOLATION
OF NUREG-1169, "TECHNICAL  
              VALVE LEAKAGE AND LEAKAGE TREATMENT METHODS" (Generic Letter 86-17)
FINDINGS RELATED TO GENERIC ISSUE C-8; BOILING WATER REACTOR MAIN STEAM ISOLATION VALVE LEAKAGE AND LEAKAGE TREATMENT  
    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
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".  
    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),
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  
  the worst single active failure, and no credit for any non-seismic Category I
11.5 SCFH at a 25 psig test pressure)  
  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.
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.
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.


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)
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:
that are related to MSIVs and LCSs that will be considered in the second, or regulatory assessment, phase of resolution.
        ° To evaluate the BWROG recommendations associated with reducing leakage past the MSIVs and assess the effectiveness of the recommendations as implemented by licensees.


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.
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.


A PRA considering the reliability and relative risks associated with the different-methods of mitigating the effects of a LOCA was performed.
A4,


The overall risks from the accident sequences in which 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.
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.


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 in another year in coordination with ongoing generic activities relating to accident source terms, to overall containment leak rate and leak rate testing considerations.
° To evaluate the use of alternate equipment to mitigate the effects of a LOCA, and potential changes in allowable MSIV leakage rates.


Neither this letter nor NUREG-1169 constitute a change in the 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.
o To identify areas in current licensing guidance (the Regulations, the


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.
* 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.


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
of the generic issue.
GOT 17 a-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 AW A:R .BWR ye .b--------:------------  
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.
--- N f --:- ----- -----NAME :JRidgely:ye  
 
: iman :G nas : TSpeis : RBerero :: E ------------  
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.
------/ ------------
 
8------------  
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.
---------DATE :IV/lv/86
 
:10 3 /86 :{V/ L/6 :f//6 :fr 8 OFFICIAL RECORD COPY  
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.
LIST L. RECENTLY ISSUED GENERIC L TERS Generic Letter No.Subject Date of Issuance GL 86-16 WESTINGHOUSE  
 
ECCS EVALUATION
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
MODELS 10/22/86 Issued To ALL PRESSURIZED
 
WATER REACTOR APPLICANTS  
GOT 17a
AND LICENSEES 6L 86-15 6L 86-14 INFORMATION  
                                                                -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.
RELATING TO COMPLIANCE  
 
WITH 10 CFR 50.49,"EQ OF ELECTRICAL  
Sincerely, Acb~ertXb     r Robert M. Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation OFC   : PSB:DBL       PSB:DBL       A:R
EQUIPMENT IMPORTANT  
                                    AW                                        .BWR
TO SAFETY" OPERATOR LICENSING EXAMINATIONS
                    ye .               b--------:------------               ---     N f --:- ----- -----
09/22/86 08/20/86 ALL LICENSEES AND HOLDERS OF AN APPLICATION
NAME :JRidgely:ye :       iman   :G       nas             : TSpeis       : RBerero         ::
FOR AN OPERATING LICENSE ALL POWER REACTOR LICENSEES  
    E ------------
AND APPLICANTS
DATE :IV/lv/86    :10 3 /86
GL 66-13 POTENTIAL  
                            ------
INCONSISTENCY
                            /
BETWEEN PLANT SAFETY ANALYSES AND TECHNICAL  
                                  :{V/ L/6    8------------   ------------
SPECIFICATIONS
                                                            :f//6          :fr        8
OL 86-12 CRITERIA FOR UNIQUE  
                                                                                                      ---------
          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
                                                          CE AND B&W
                                                          PRESSURIZED
                                                          WATER REACTORS
OL   86-12   CRITERIA FOR UNIQUE  


==PURPOSE==
==PURPOSE==
EXEMPTION  
07/03/66    ALL NON-POWER
FROM CONVERSION  
            EXEMPTION FROM CONVERSION FROM                REACTOR
FROM THE USE OF HEU FUEL 07/23/86 07/03/66 ALL POWER REACTOR LICENSEES  
            THE USE OF HEU FUEL                         LICENSEES
WITH CE AND B&W PRESSURIZED
                                                        AUTHORIZED TO
WATER REACTORS ALL NON-POWER REACTOR LICENSEES AUTHORIZED  
                                                          USE HEU FUEL
TO USE HEU FUEL GL 66-11 6L 66-10 DISTRIBUTION  
GL   66-11 DISTRIBUTION OF PRODUCTS         06/25/86    ALL NON- POWER
OF PRODUCTS IRRADIATED  
            IRRADIATED IN RESEARCH                     REACTOR
IN RESEARCH REACTORS IMPLEMENTATION  
            REACTORS                                     LICENSEES
OF FIRE PROTECTION
6L  66-10  IMPLEMENTATION OF FIRE         04/28/86     ALL POWER
REQUIREMENTS
            PROTECTION REQUIREMENTS                      REACTOR
06/25/86 04/28/86 ALL NON- POWER REACTOR LICENSEES ALL POWER REACTOR LICENSEE AND APPLICANTS
                                                        LICENSEE AND
6L 86-09 TECHNICAL  
                                                        APPLICANTS
RESOLUTION  
6L   86-09 TECHNICAL RESOLUTION OF        03/31/86    ALL BWR AND
OF GENERIC ISSUE NO. B-59 (N-1) LOOP OPERATION  
            GENERIC ISSUE NO. B-59                       PWR LICENSEES
IN BWRS AND PWRS GL 86-08 AVAILABILITY  
            (N-1) LOOP OPERATION IN BWRS               AND APPLICANTS
OF SUPPLEMENT  
            AND PWRS
4 TO NUREG-0933, "A PRIORITIZATION  
GL 86-08   AVAILABILITY OF SUPPLEMENT 4    03/25/86    ALL LICENSEES,
OF GENERIC SAFETY ISSUES" GL B6-07 TRANSMITTAL  
            TO NUREG-0933, "A                           APPLICANTS AND
OF NUREG-1190
            PRIORITIZATION OF GENERIC                   CONSTRUCTION
REGARDING  
            SAFETY ISSUES"                               PERMIT HOLDERS
THE SAN ONOFRE UNIT 1 LOSS OF POWER AND WATER HAMMER EVENT 03/31/86 03/25/86 03/20/86 ALL BWR AND PWR LICENSEES AND APPLICANTS
GL B6-07   TRANSMITTAL OF NUREG-1190       03/20/86    ALL LICENSEES
ALL LICENSEES, APPLICANTS
            REGARDING THE SAN ONOFRE UNIT               AND APPLICANTS
AND CONSTRUCTION
            1 LOSS OF POWER AND WATER
PERMIT HOLDERS ALL LICENSEES AND APPLICANTS
            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.
 
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.


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 :KA WR D:SRO Ae D:BWR--- --- -- -- --- --X----- :- -- -- -- -: -- ----: NAME :JRidgely:ye  
Sincerely, Robert M. Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation OFC : PSB:DBL       PSB:DBL         Ae WR
: iman :G nas : TSpeis : RBer ero : DATE :01S1t/86  
                                  :KA               D:SRO             D:BWR
:1IG3 /86 :10/ /86 :10/ /86 :19/rI /86 OFFICIAL RECORD COPY}}
          ---
          -               --   --      X-----     :-   -- --   -- -:   --   ----   : -- - -- - -
NAME :JRidgely:ye :       iman   :G       nas   : TSpeis           : RBer ero     :
DATE :01S1t/86     :1IG3 /86       :10/       /86 :10/       /86     :19/rI /86 OFFICIAL RECORD COPY}}


{{GL-Nav}}
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Latest revision as of 03:48, 24 November 2019

NRC Generic Letter 1986-017: Availability of NUREG-1169, Technical Findings Related to Generic Issue C-8; Boiling Water Reactor Main Steam Isolation Valve Leakage & Leakage Treatment Methods
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)
v • d • e


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

AW .BWR

ye . b--------:------------ --- N f --:- ----- -----

NAME :JRidgely:ye : iman :G nas  : TSpeis  : RBerero  ::

E ------------

DATE :IV/lv/86 :10 3 /86

/

{V/ L/6 8------------ ------------
f//6 :fr 8

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

CE AND B&W

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

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