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MONTHYEARML19309H8111980-05-0808 May 1980
Forwards IE Info Notice 80-20, Loss of Decay Heat Removal Capability at Davis-Besse Unit 1 While in Refueling Mode. No Response Required
Project stage: Other
ML19318B8961980-06-0505 June 1980
Responds to IE Bulletin 80-12, Decay Heat Removal Sys Operability. Plant Design Does Not Provide for Automatic Actuation of ECCS Recirculation or Automatic Positioning of Containment Recirculation Sump Valves
Project stage: Other
ML20008E2951980-10-14014 October 1980
Responds to NRC Re Proposed Tech Spec Changes for All Facilities to Provide for Redundancy in Decay Heat Removal Capability.Plant Specs Already Address Concerns & Require No Changes
Project stage: Other
ML20010E8541981-08-14014 August 1981
Requests That Proposed Tech Specs for Redundancy of Decay Heat Removal Capability in All Modes of Operation & Related Safety Analysis Be Submitted within 60 Days.Model Tech Specs to Assist in Preparation of Submittal Encl
Project stage: Other
ML20038B1351981-11-16016 November 1981
Tech Spec Change Request 72 for Amend to License DPR-24 & DPR-27,changing Tech Specs 15.3.1,15.3.3 & 15.3.8 to Ensure Redundancy of Decay Heat Removal Capability Under All Operating Conditions
Project stage: Other
ML20038B1461981-11-16016 November 1981
Proposed Tech Specs Sections 15.3.1,15.3.3. & 15.3.8 to Ensure Redundancy of Decay Heat Removal Capability Under All Operating Conditions
Project stage: Other
ML20039C4011981-11-18018 November 1981
Comments on Util Tech Spec Change Request 72,proposing Revision to Tech Spec 15.3.1.A.2(a) Re Redundancy of Decay Heat Removal Sys.Elimination of Decay Heat Removal Capability Above 350 F Inappropriate
Project stage: Other
ML20039C4191981-12-0909 December 1981
Interim Deficiency Rept DER 81-39 Re Unit 1.Gas Stripper by C-E Has Undocumented Section of Pipe & Welds in Violation of ASME Code,Initially Reported 811112.Evaluation & Final Rept Expected by 820129
Project stage: Other
ML20039C3981981-12-21021 December 1981
Forwards Region 3 Comments Re Util Tech Spec Change Request 72
Project stage: Other
ML20040H0251982-01-22022 January 1982
Informs That 811116 Proposed Amend to Tech Specs Re Establishment of Redundancy of Decay Heat Removal Capability During All Modes of Operation Is Unacceptable.Application Should Be Modified
Project stage: Other
ML20052D8061982-05-0303 May 1982
Advises That Westinghouse Will Not File Reply Brief in Response to Wi Environ Decade Brief.Svc List Encl
Project stage: Request
ML20052E9091982-05-0303 May 1982
Revised Application for Amend to Licenses DPR-24 & DPR-27 Consisting of Changes to Tech Specs to Provide Addl Assurance of Availability of Redundant Reactor Decay Heat Removal Capabilities
Project stage: Request
ML20052E9201982-05-0303 May 1982
Proposed Changes to Tech Specs to Provide Addl Assurance of Availability of Redundant Reactor Decay Heat Removal Capabilities
Project stage: Request
ML20027D2131982-07-31031 July 1982
Tech Spec for Redundant DHR Capability,Point Beach,Units 1 & 2
Project stage: Other
ML20069L7481982-11-0808 November 1982
Safety Evaluation Supporting Amends 66 & 71 to Licenses DPR-24 & DPR-27,respectively
Project stage: Approval
ML20069L7521982-11-0808 November 1982
Notice of Issuance & Availability of Amends 66 & 71 to Licenses DPR-24 & DPR-27,respectively
Project stage: Other
ML20069L7421982-11-0808 November 1982
Amend 66 & 71 to Licenses DPR-24 & DPR-27,respectively, Upgrading Tech Specs to Provide Redundancy of DHR Capability in All Modes of Operation
Project stage: Other
ML20081D3121983-10-25025 October 1983
Application to Amend Licenses DPR-24 & DPR-27,changing Tech Spec 15.3.1.A to Eliminate Provisions Beyond Basis for Required Operational Components of Rcs.Class II Fee Encl
Project stage: Request
ML20081D3241983-10-25025 October 1983
Proposed Changes to Tech Spec 15.3.1.A Eliminating Provisions Beyond Basis for Required Operational RCS Components
Project stage: Request
ML20086M6131984-02-0202 February 1984
Safety Evaluation Supporting Amends 82 & 86 to Licenses DPR-24 & DPR-27,respectively
Project stage: Approval
ML20086M6031984-02-0202 February 1984
Amends 82 & 86 to Licenses DPR-24 & DPR-27,respectively, Clarifying Limiting Condition for Operation of Steam Generators & Other DHR Equipment,Indicating Conditions Only Applicable When Fuel Loaded in Core
Project stage: Approval
1981-12-09
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Wisconsin Electnc eomcoma 231 WEST MICHIGAN, MILWAUKEE, WISCONSIN 53201 June 5, 1980 Mr. J.
G.
Keppler, Regional Director Office of Inspection and Enforcement, Region III U.
S. NUCLEAR REGULATORY COMMISSION 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
DOCKET NOS. 50-266 AND 50-301 RESPONSE TO IE BULLETIN NO. 80-12 POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 This letter is in response to IE Bulletin No. 80-12 entitled " Decay Heat Removal System Operability".
The circum-stances and events surrounding the Davis-Besse Unit 1 loss-of-decay heat removal (DHR) capability incident have been appropriately reviewed.
This review included circulation of the Davis-Besse Sequence of Events among Operations Group supervisors.
Decay heat removal hardware capability and operating history for Point Beach Nuclear Plant and relative to the Davis-Besse incident were reviewed in accoraance with the bulletin.
The design of Point Beach Nuclear Plant does not provide for automatic actuation of ECCS recirculation or automatic posi-tioning of containment recirculation sump valves.
Present Point Beach operating procedure OP-3C requires automatic safety injection (except as actuated by High containment pressure) be manually blocked at a reactor coolant system pressure of 1765 psig during the approach to cold shut-down.
1 We are currently implementing a change to procedure PBNP 4.13, " Equipment Isolation Procedure" (Operating Point l
Beach Nuclear Plant Administrative Control Policies and Procedures Manual, Volume 1), to assure redundance and integrity of DHR capability.
The procedure change is as follows:
"2.0 PRECAUTIONS AND LIMITATIONS To ensure the safety of the nuclear reactor and that of the general public, it is important to ensure that at least two trains of redundant methods of removing decay heat from the reactor are maintained at all times.
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$80% [V 8006800- g f
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Mr. J.
G.
Keppler June 5, 1980 This condition can be met by having two fully operable trains of residual heat removal or if one train is to be removed from operable status, then the redundancy for decay heat removal must be provided by an operable steam generator with reactor coolant system flow capability by either natural convection or forced circulation.
Any deviations from this requirement must be approved by the Manager's Supervisory Staff prior to tag series imple-mentation."
The safeguards against DHR degradation and their adequacy are described in the Point Beach Nuclear Plant Final Facility Description and Safety Pnalysis Report Sections 9.3
( Auxiliary and Emergency Systems), 6.2.2 (Engineered Safety Features), and 8.0 (Electrical Systems).
Reviews performed in accordance with IE Bulletin No.
80-12 did not identify any modifications to the residual heat removal system which would affect decay heat removal or safety function ability.
Thus, the residual heat removal system remains safe and adequate as described in the above-re"erenced FFDSAR sections.
Very truly yo,urs, Q
h6v!
C.
W.
Fay, Director i
Nuclear Power Department Subacribed and sworn to before me
'this'9th day of Ju 1980.
A.
iotdry Public, S te of Wisconsin My Commission e pires d/)L4/ /f t
/
Copies to Director, Division of Reactor Operations Inspection NRC Office of Inspection and Enforcement Washington, D.
C.
20555 NRC Resident Inspector, Point Beach Nuclear Plant L
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