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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20211K8611999-09-0101 September 1999 Informs That There Has Been Some Confusion Re Recently Issued ODCM Generic Section Rev Which Needs to Be Clarified. Clarifications Are Listed ML20210P1361999-08-0404 August 1999 Notification of 990817 Meeting with Util in Rockville, Maryland to Discuss Status of Licensing Actions Submitted by Comm Ed & Plan for Proposed Licensing Workshop ML20196H4831998-12-0202 December 1998 Forwards Facility Submitted Outline,Exam Submittal & as Given Operating Exam for Test Administered During Wk of 981026 at Dresden Nuclear Power Station ML20237E3131998-08-26026 August 1998 Forwards for Public Release,Info Re NRC SMM Held on 980714-15.Summary of January 1998 NRC SMM & Watch List Removal Evaluation Factors Also Encl ML20249B8451998-06-17017 June 1998 Notification of 980723 Meeting W/Util in Morris,Il to Inform Public of Licensee Plans for Decommissioning Plant,Unit 1 ML20216H6971998-03-17017 March 1998 Notification of 980326 Meeting W/Commonwealth Edison Co in Lisle,Il to Discuss Comed Request to Consolidate near-site Emergency Operations Facility Into Single Central EOF ML20211Q8741997-10-16016 October 1997 Notification of Significant Licensee Meeting W/Util on 971028 to Discuss Apparent Violations Described in to Js Perry ML20217D4261997-09-30030 September 1997 Informs of Scheduled Visits W/Nuclear Services at Gpu on Nov 14th & Visit at Commonwealth Edison on Dec 3rd & Would Like to Receive Any Info Available.Supporting Documentation Encl ML20197B9141997-07-23023 July 1997 Forwards Safety Evaluation Re Concrete Expansion Anchor Safety Factors for High Energy Line Break Restraints,In Response to Region III 960920 Request ML20148D1981997-05-28028 May 1997 Forwards Signed Original of Order Prohibiting Involvement in NRC-licensed Activities (Effective Immediately),For Transmittal to Ofc of Fr,For Publication.W/O Encl ML20138J9791997-05-0707 May 1997 Notification of 970520 Meeting W/Commonwealth Edison in Rockville,Md to Discuss Commonwealth Edison Quality Initiatives & Plans for Dry Storage at Dresden ML20217D5461997-04-18018 April 1997 Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission IA-97-178, Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission1997-04-18018 April 1997 Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission ML20147J2391997-04-0909 April 1997 Notification of Meeting on 970416 W/Util in Rockville,Md to Discuss Overall Response & Present Addl Details Re Performance Indicators Used to Monitor Performance Stations ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20149M0471996-12-10010 December 1996 Forwards Internet Mail Received from PM Blanch ML20210N4271996-12-0202 December 1996 Informs About Drop in Meeting on 961203 for Update on Industry Restructuring & Deregulation,Unicom Strategic Planning & Mixed Oxide Fuel ML20217D5421996-11-27027 November 1996 Forwards Partially Withheld Background Briefing Package in Preparation for 961203 Meeting Between Comed,Nuclear Strategic Services & Chairman Jackson ML20210N3761996-08-12012 August 1996 Informs About Meeting on 960513 to Brief Chairman Jackson on Comed Response to Deregulation ML20217D4761996-07-31031 July 1996 Forwards Background Briefing Package in Prepartion of 960813 Meeting Between Commonwealth Edison Co & Chairman Jackson. Purpose of Visit to Discuss Recent Organizational Changes at Comed & Company Mgt Focus for Immediate Future ML20210N3381996-05-14014 May 1996 Discusses Courtesy Visit to Ceco on 960513 Re Listed Plants ML20210N2951996-05-0101 May 1996 Discusses Pre Briefing for Meeting on 960513 Re Mgt, Operations,Maint & Engineering ML20210N2681995-11-13013 November 1995 Discusses Paritially Withheld Chairman Briefing by Ceco on 951116 ML20217D5321995-11-0909 November 1995 Forwards Partially Withheld Background Briefing Package in Preparation for 951116 Meeting Between Commission & Senior Comed Mgt.Purpose of Visit to Discuss Performance at Each of Sites & Challenges & Issues Needed to Be Addressed ML20210N3971995-10-12012 October 1995 Informs of Courtesy Visit on 951011 to Util to Discuss Listed Topics.List of Attendees Encl ML20210N3701995-10-0505 October 1995 Forwards Background Briefing Package in Preparation for 951011 Meeting W/Company Executives & Chairmam Jackson ML20149D8681994-05-16016 May 1994 Forwards Signed Copy of Notice of Availability for Generic Communication That Has Been Issued for Transmittal to Ofc of Fr for Publication ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20248E7601994-02-16016 February 1994 Forwards Rept of Unit One Investigative Team Re 940202 Request to Review Unit 1 Off Gas Filter Bldg Water Pipe Leak Event,Unit 1 Sphere Water Pipe Leak Event & Various Issues Related to Unit 1 Fuel Storage ML20058N4811993-12-15015 December 1993 Informs of Decision to Expand Senior Mgt Oversight of Selected Plants,Per Recent Meeting W/J Martin & H Miller. Lists Assignment of Managers,Effective Immediately ML20062J4501993-10-27027 October 1993 Requests Addl Info Re Proposed EAL Changes in Util Generating Station Emergency Plan Annexes.Proposed EALs Reviewed Against Guidance in NUMARC/NESP-007,rev 2, Methodology for Development of Eals ML20059A4651993-10-20020 October 1993 Notification of Significant Licensee Meeting W/Util in Glen Ellyn,Il on 931104 to Review Status of Util Initiatives on QA & Corporate Engineering Support ML20057C9801993-09-27027 September 1993 Discusses 930927 Press Conference Re J O'Connor Announcement That Util Settled Six Rate Matters & Appeals Before Illinois Courts & Commerce Commission by Agreeing to Refund Listed Amount to Customers Over Next 12 Months ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both 1999-09-01
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20211K8611999-09-0101 September 1999 Informs That There Has Been Some Confusion Re Recently Issued ODCM Generic Section Rev Which Needs to Be Clarified. Clarifications Are Listed ML20210P1361999-08-0404 August 1999 Notification of 990817 Meeting with Util in Rockville, Maryland to Discuss Status of Licensing Actions Submitted by Comm Ed & Plan for Proposed Licensing Workshop ML20196H4831998-12-0202 December 1998 Forwards Facility Submitted Outline,Exam Submittal & as Given Operating Exam for Test Administered During Wk of 981026 at Dresden Nuclear Power Station ML20237E3131998-08-26026 August 1998 Forwards for Public Release,Info Re NRC SMM Held on 980714-15.Summary of January 1998 NRC SMM & Watch List Removal Evaluation Factors Also Encl ML20249B8451998-06-17017 June 1998 Notification of 980723 Meeting W/Util in Morris,Il to Inform Public of Licensee Plans for Decommissioning Plant,Unit 1 ML20216H6971998-03-17017 March 1998 Notification of 980326 Meeting W/Commonwealth Edison Co in Lisle,Il to Discuss Comed Request to Consolidate near-site Emergency Operations Facility Into Single Central EOF ML20211Q8741997-10-16016 October 1997 Notification of Significant Licensee Meeting W/Util on 971028 to Discuss Apparent Violations Described in to Js Perry ML20217D4261997-09-30030 September 1997 Informs of Scheduled Visits W/Nuclear Services at Gpu on Nov 14th & Visit at Commonwealth Edison on Dec 3rd & Would Like to Receive Any Info Available.Supporting Documentation Encl ML20197B9141997-07-23023 July 1997 Forwards Safety Evaluation Re Concrete Expansion Anchor Safety Factors for High Energy Line Break Restraints,In Response to Region III 960920 Request ML20148D1981997-05-28028 May 1997 Forwards Signed Original of Order Prohibiting Involvement in NRC-licensed Activities (Effective Immediately),For Transmittal to Ofc of Fr,For Publication.W/O Encl ML20138J9791997-05-0707 May 1997 Notification of 970520 Meeting W/Commonwealth Edison in Rockville,Md to Discuss Commonwealth Edison Quality Initiatives & Plans for Dry Storage at Dresden ML20217D5461997-04-18018 April 1997 Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission IA-97-178, Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission1997-04-18018 April 1997 Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission ML20147J2391997-04-0909 April 1997 Notification of Meeting on 970416 W/Util in Rockville,Md to Discuss Overall Response & Present Addl Details Re Performance Indicators Used to Monitor Performance Stations ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20149M0471996-12-10010 December 1996 Forwards Internet Mail Received from PM Blanch ML20210N4271996-12-0202 December 1996 Informs About Drop in Meeting on 961203 for Update on Industry Restructuring & Deregulation,Unicom Strategic Planning & Mixed Oxide Fuel ML20217D5421996-11-27027 November 1996 Forwards Partially Withheld Background Briefing Package in Preparation for 961203 Meeting Between Comed,Nuclear Strategic Services & Chairman Jackson ML20210N3761996-08-12012 August 1996 Informs About Meeting on 960513 to Brief Chairman Jackson on Comed Response to Deregulation ML20217D4761996-07-31031 July 1996 Forwards Background Briefing Package in Prepartion of 960813 Meeting Between Commonwealth Edison Co & Chairman Jackson. Purpose of Visit to Discuss Recent Organizational Changes at Comed & Company Mgt Focus for Immediate Future ML20210N3381996-05-14014 May 1996 Discusses Courtesy Visit to Ceco on 960513 Re Listed Plants ML20210N2951996-05-0101 May 1996 Discusses Pre Briefing for Meeting on 960513 Re Mgt, Operations,Maint & Engineering ML20210N2681995-11-13013 November 1995 Discusses Paritially Withheld Chairman Briefing by Ceco on 951116 ML20217D5321995-11-0909 November 1995 Forwards Partially Withheld Background Briefing Package in Preparation for 951116 Meeting Between Commission & Senior Comed Mgt.Purpose of Visit to Discuss Performance at Each of Sites & Challenges & Issues Needed to Be Addressed ML20210N3971995-10-12012 October 1995 Informs of Courtesy Visit on 951011 to Util to Discuss Listed Topics.List of Attendees Encl ML20210N3701995-10-0505 October 1995 Forwards Background Briefing Package in Preparation for 951011 Meeting W/Company Executives & Chairmam Jackson ML20149D8681994-05-16016 May 1994 Forwards Signed Copy of Notice of Availability for Generic Communication That Has Been Issued for Transmittal to Ofc of Fr for Publication ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20248E7601994-02-16016 February 1994 Forwards Rept of Unit One Investigative Team Re 940202 Request to Review Unit 1 Off Gas Filter Bldg Water Pipe Leak Event,Unit 1 Sphere Water Pipe Leak Event & Various Issues Related to Unit 1 Fuel Storage ML20058N4811993-12-15015 December 1993 Informs of Decision to Expand Senior Mgt Oversight of Selected Plants,Per Recent Meeting W/J Martin & H Miller. Lists Assignment of Managers,Effective Immediately ML20062J4501993-10-27027 October 1993 Requests Addl Info Re Proposed EAL Changes in Util Generating Station Emergency Plan Annexes.Proposed EALs Reviewed Against Guidance in NUMARC/NESP-007,rev 2, Methodology for Development of Eals ML20059A4651993-10-20020 October 1993 Notification of Significant Licensee Meeting W/Util in Glen Ellyn,Il on 931104 to Review Status of Util Initiatives on QA & Corporate Engineering Support ML20057C9801993-09-27027 September 1993 Discusses 930927 Press Conference Re J O'Connor Announcement That Util Settled Six Rate Matters & Appeals Before Illinois Courts & Commerce Commission by Agreeing to Refund Listed Amount to Customers Over Next 12 Months ML20057C0051993-08-31031 August 1993 Staff Requirements Memo Re SECY-93-221, Approval of Decommissioning Plan & Amend of License for Dresden Nuclear Power Station,Unit 1 ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246D8841989-06-19019 June 1989 Staff Requirements Memo Re 890601 Briefing on Operating Reactors & Fuel Facilities in Rockville,Md.Commission Expressed Disappointment in Long Term Operating Performance of Turkey Point Nuclear Power Plant ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl 1999-09-01
[Table view] |
Text
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NUCLEAR REGULATORY COMMISSION fg' i s-
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- MAY 0 21983 MEMORANDUM FOR: D. G. Eisenhut, Director, Division of Li, censing, NRR k
FR0ti: C. E. Norelius, Director, Division of Project and Resident Programs
~
SUBJECT:
REQUEST FOR TECHNICAL ASSISTANCE TO DELINEATE APPROPRIATE LICENSEE ACTIONS FOLLOWING FAILURE OF.CERTAIN ECCS/
CONTAINMENT ISOLATION VALVES - -
An inc'ident recently occurred at Dresden Unit 3, that requires further clarification by your office. During'a surveillance on the Low Pressure -
Coolant Injection (LPCI) System, a motor operated suction valve (1501-50) for one of the LPCI pumps failed to cycle correctly. The valve, which is Aormally.left in the open position, was closed during the surveillance and
,. could not be reopened from the control room. To preclude declaring the LPCI system inoperable,'the valve' was manually opened and electrically disarmed, o According to Dresden's. Updated Final Safety Analysis Report (UFSAR), this t valve and other similar low pressure' Emergency Core Coolino Systems (ECCS) suction valves perform containment isolation functions. Section 6.2.4.2.4.5 of the UFSAR states in part:
"Because the low pressure ECCS piping outside the drywell up to the first outside isolation valve is considered a logical extension of the primary containment, the piping must meet the same design, surveillance and testing criteria as the primary containment. . . All leakage in the ECCS outside the primary containment can be isolated from the suppression chamber and the primary system itself."
In addition, these valves also appear in the UFSAR table: 5.2.2.5, " Principle F'e netrations of Primary Containment and Associated Isolation Valves."
( s 8707100000 870701 PDR FOIA WILLIAM 87-121 PDR
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D. G. Eisenhut MAY 0 21983
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The Dresden Technical Specifications do not address these' valves as containment -
isolation valves. These valves do not have the automatic closure initiation as other isolation valves because they are required to be'open to support ECCS operation and therefore are exempt from the automatic closure function.
It is. our understanding however, that these valves must be capable of being closed by-operator action from the control room or another remote ,
operator in the plant in the event of excess leakage from the system to l effect containment isolation.
~
The Resident Inspectors identified to the licensee that these valves perform
- a primary containment isolation function according to their UFSAR, and were not capable of performing that function with the_ valve 'open and electrically deactivated. The licensee started to electrically reconnect the valve.
~
In the mean time,' the valve was repaired and placed in service. )
These valves were also a subject of the Systematic Evaluation Program (SEP), '
Topic VI-4, and are identified under integrated as -sment 4.18.2 in iNUREG-0823. The staff position was ". . . that adequate leakage detection
- and appropriate procedures for operator action should be provided and the operating station should be relocated to an accessible area, where necessary . . ."
This situation raises several questions:
- 1. The LPCI (1501-50) valve has an automatic open signal which opens the valve if closed when an ECCS automatic initiation signal is received.
The automatic open portion of the valve was not operable because when the valve closed it was incapable of being automatically opened. Would'the valve be considered inoperable or operable with only the automatic open capability inoperable, and the valve was open with the capability of closing?
The regional position is that if any automatic function of an ECCS or ~ Containment Isolation becomes inoperable the valve is inoperable.
The valve must be considered inoperable even if the automatic function is not presently needed (e.g., valve open and automatic open function not operable).
- 2. When an ECCS/ Containment Isolation valve is declared inoperable, what is the correct action to be taken by the licensee? Should the valve be placed in the open position thereby maintaining the operable status of that ECCS loop but violating the Technical Specification definition of primary containment? Or, should the valve be placed in the closed position, and in that way maintain primary containment, but by the same action, enter a Limiting Condition for Operation (LCO) for the affected system?
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,D. G. Eisenhut MAY 0 21983 The regional position'is that the licensee should t ke~ the most conservative approach to the problem. The valve should be closed to maintain primary containment and the appropriate 100 should be entered.. However, if only the automatic open function. is inoperable.
the valve may be opened while keeping- closure capability, declare the valve inoperable, and take the action of the LCO associated with an inoperable. ECCS system.
~
! 3. Once an ECCS/ Containment Isolation valve is declared inoperable and the valve is then placed in a designated configuration (either open or closed), should the valve be electrically deactivated to prevent a possible automatic initiation from causing _the valve configuration to change? (An example would be closure of the 1501-5D valve and electrically deactivating it to prevent an automatic initiation of LPCI to reopen the valve). Should an automatic initiation, in this case, be intentionally bypassed?
_. ; The regional position is that the valve should remain open if remote closure is possible. If this is not the case, the valve should be closed to provide. containment isolation and it should be electrically disarmed to prevent reopening. In either case, the appropriate LCO' for inoperable ECCS system should be entered.
- 4. Since the valve was not in the Technical Specifications, the associated action statement was not apparent to the licensee. Should ECCS pump suction valves (LPCI and Core Spray)' be included in the Technical Specifications to identify the action to be taken when they become inoperable? If this is affimative, Table 3.7.1 of the Dresden Unit 2 and 3 Technical Specifications, should be changed to include the valves.
The regional position is that these valves should be included in Technical Specifications and appropriate action statements should be added.
- 5. The SEP topic recommendation was that appropriate procedures for operator action should be provided. The licensee had not issued
.- these procedures. Under what conditions would these valves be required to be closed?
The regional position is that these valves should be closed in the event of excess leakage, or if the capability of closing the valve remotely becomes inoperable.
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D. G. Eisenhut MAY 0 21983 s
These questions are naturally of great concern. We therefore request your response to these questions by June 1,1983. Any clarification your office can bring to this matter is appreciated.
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. C. E. Norelius, Director Division of Project and
~ ; Resident Programs cc: R. Wessman, NRR ,
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UNITED STATES y j NUCLEAR REGULATORY COMMISSION
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JUN 2 91983 M(RQ,J waI (
" 2 ?_.l _.W LI l i MEMORANDUM FOR: Charles E. Norelius, Director Onm i he i p 5;Ifp l g j Division of Project and Resident Programs 2 { ; i g Region III iii. t 1 l y FROM: Darrell G. Eisenhut, Director OL i WI lei fl Division of Licensing, NRR
SUBJECT:
TECHNICAL ASSISTANCE TO DELINEATE APPROPRIATE LICENSEE ACTIONS FOLLOWING FAILURE OF CERTAIN .
ECCS/ CONTAINMENT ISOLATION VALVES
REFERENCE:
Memorandum from C. E. Norelius to D. G. Eisenhut, Dated May 2,1983,
Subject:
" Request for Technical Assistance to Delineate Appropriate Licensee Actions Following Failure of Certain ECCS/
Containment Isolation Yalves."
l l
The referenced memorandum requests NRR's position concerning licensee actions }
following the failure of certain ECCS/ containment isolation valves in regard '
to incidents which had recently occurred at Dresden Unit 3. In your memorandum, you raised five questions and offered the regional position on each of these five questions. Your questions and the regional positions are restated below and are followed b- "o.R's position.
Question 1 .
The LPCI (1501-50) valve has an automatic open signal which opens the valve if closed when an ECCS automatic initiation signal is received. The automatic open portion of the valve was not operable because when the valve closed it was incapable of being automatically opened. Would the valve be considered. inoperable or operable with only the automatic open capability inoperable, and the valve was open with the capability of closing?
The regional position is that if any automatic function of an ECCS or Containment Isolation becomes inoperable the valve is inoperable.
The valve must be considered inoperable even if the automatic open function is not presently needed (e.g., valve open and automatic open function not operable).
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. "~' tharles E. Norelius, Director .
JUN 2 91983
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. Response - - ' -
We concur with the regional position on this matter. Such a position is consistent our intent as expressed in our Standard Technical Specifi-cation definition of Operable-Operability which all power reactor licensees were requested to adopt via our generic letter of April 10, 1980. It is our position that if any function of the LPCI valve is inoperable, the valve must be declared inoperable. Furthermore, since opening of the valve is required for the LPCI system to perform its intended function, the LPCI system also must be declared inoperable.
Question 2 When an ECCS/ Containment Isolation valve is declared inopera'ble, what
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is the correct action to be taken by the licensee? Should the valve be placed in the open position thereby maintaining the operable status of that ECCS loop but violating the Technical Specification definition of primary containment? Or, should the valve be placed in the closed !
position, and in that way maintain primary containment, but by the same action, enter a Limiting Condition for Operation (LCO) for the affected sys tem?
The regional position is th'at the licensee should take the most con-servative. approach to the problem. The valve should be closed to maintain primary containment and the appropriate LC0 should be entered. However, if only the automatic open function is inoperable the valve may be opened while keeping closure capability, declare the valve inoperable, and take the action of the LC0 associated with an inoperable ECCS system.
Response
l Our position on this question is that the licensee should follow the <
requirements of the applicable technical specification. In the event '
the applicable technical specification does not provide explicit criteria for positioning an inoperable ECCS/ Containment Isolation valve, we would generally concur with the regional position that the valve should be closed so as to maintain containment integrity. Furthermore, the ECCS l loop should be declared inoperable and its action statement complied !
with. In the case where such a valve was inoperable solely as a result l of being unable to automatically open, we would consider it acceptable j to maintain the valve in an open position provided the ECCS loop was 4 declared inoperable, its action statement was complied with, and the i valve was capable of being closed by an automatic containment isolation signal. i l
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Charles E. Norelius, Director 393 7 9 ) g3 Question 3 Once an ECCS/ Containment Isolation valve is declared inoperable and the valve is then placed in a designated configuration (either open or closed), should the valve be electrically deactivated to prevent a possible automatic initiation from causing the valve configuration to change? (An example would be closure of the 1501-5D valve and electrically deactivating it to prevent an automatic initiation of LPCI to reopen the valve). Should an automatic initiation, in this case, be intentionally bypassed?
The regional position is that the valve should remain open if remota closure is possible. If this is not the case, the valve should be -
closed to provide containment isolation and it should be electrically disarmed to prevent reopening. In either case, the appropriate LC0 for inoperable ECCS system should be entered.
Response
If, as discussed in our response to your Question 2, an inoperable valve is closed to maintain containment integrity, it is our position that this valve should be electrically deactivated to preclude its subsequent inadvertent actuation. However, if a valve is inoperable and is being maintained in its open position in accordance with the criteria given in our response to your Question 2, it is our position that this valve should not be electrically deactivated since it would then be incapable of closing to provide containment isolation. Furthermore, we do not believe that automatic initiation of the ECCS loop should be bypassed. ,
i Question 4 Since the valve was not in the Technical Specifications, the associated action statement was not apparent to the licensee. Should ECCS pump suction valves (LPCI and Core Spray) be included in the Technical Specifications to identify the action to be taken when they become inoperable? If this is affirmative, Table 3.7.1 of the Dresden Unit 2 and 3 Technical Specifications, should be changed to include the valves.
The regional position is that these valves should be included in Technical Specifications and appropriate action statements should be added.
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Charles E. Norelius, Director p 2 9 1983 l
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Response
As part of the ECCS systems, these valves would not normally be listed separately since the definition of Operable-Operability (which all power reactor licensees were requested to adopt via our generic letter,of April 10, 1980) would require these valves to be operable in order.for the ECCS systems to be operable. However, since these valves are considered as. part of the boundary for containment isolation, it is our position that they should be included in Table 3.7.1, Primary Containment Isolation, of the Dresden Unit 2 and Unit 3 Technical Specifications and we will request the licensee to submit a licensee amendment to add them to Table 3.7.1.
Question 5 .
The SEP topic recommendation was that appropriate procedures for operator action ~should be provided. The licensee had not issued these procedures.
Under what conditions would these valves be required to be closed? .
The regional position is that these valves should be closed in the event of excess leakage, or if the capability of closing the valve remotely becomes inoperable.
Response ,
As previously stated in our response to Question 2, our position is that the licensee should follow the requirements of the applicable technicti specification. In the event the applicable technical specification does not provide explicit criteria for positioning an inoperable ECCS/Contain-ment Isolation valve, we concur with the regional position that, in general, the valve should be closed so as to maintain containment integrity. Further-more, the ECCS loop should be declared inoperable and its action statement !
complied with. In the case where such a valve was inoperable solely as a result of being unable to automatically open, we would consider it acceptable to maintain the valve in an open position provided the ECCS loop was declared i inoperable, its action statement was complied with, and the valve was capable !
of being closed by an automatic containment isolation signal. However, there may be situations which can arise which will dictate different actions be '
taken concerning the disposition of these valves and they should be addressed l on a plant specific basis by the licensee.
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Darrell G. Ei'f[,01 senYu ,Q Md Director Division of Licensing ;
Office of Nuclear Reactor Regulation w