ML20043H948
| ML20043H948 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/18/1990 |
| From: | Nichols S Maine Yankee |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-83-28, GL-90-04, GL-90-4, MN-90-61, SEN-90-182, NUDOCS 9006270117 | |
| Download: ML20043H948 (11) | |
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- MaineYankee:
RELLABLE ELECTRICITY FOR MAINE SANCE 1972 '
- EDISON DRIVE. AUGUSTA, MAINE 04330. (207) 622 4868
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!) 3 June 18, 1990 MN-90-61 SEN-90-182
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UNITED STATES-NUCLEAR REGULATORY COMMISSION Attention:- Document Control Desk p
Washin'gton'7DC,20055
References:
(a)_ License'No. DPR-36 (Docket No. 50-309)
(b).USNRC Letter dated April 25, 1990,- Request for Information on the Status of Implementation of Generic Safety Issues: Resolved
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with-Imposition of Requirements.or Corrective Actions'(Generic l
' Letter 90-04)-
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Subject:
LResponse:to' Generic letter 9'J-04, Implementation of Generic Safety Issues
.(GSI)-Requirements-
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' Gentlemen:.
m EMaine', Yankee has reviewed the status;of implementation of Generic Safety Issues, N
.as requested and" identified in ' Reference (b).. Attached is ~an annotated cuy of M
Enclosure;(1) of Reference-(b). We have marked the attachment with our judgement of status 3 based on a review of our records for each item as applicable to Maine Yankee.
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This status report is not intended to make any commitments for Maine Yankee or modify N
- any previous commitments. Also, please note the> attachment!provides-expected-dates t of -implementation for several pending items.
Maine-Yankee considers these dates J
tentative based on our current plans.
'Should:youthave any que cions'on the attached, please contact me.
Very truly yours,.
Q AAc S. E. Nichols Licensing Section Head u
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Attachment:
(Annotated Enclosure (1) of Generic Letter 90-04)
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Mr. Thomas T. Martin
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MrG Richard J. Freudenberger 4'
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ATTACHMENT p
' Annotated Copy of Enclosure (1) of NRC Generic Letter 90..
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Maine Yankee Atomic Power Company DOCKET NO.: 309 1
. LICENSEE:
Maine Yankee Atomic Power. Company
.' STATUS OF LICENSEE IW LEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITN IMPOSITION OF-REQUIREMENTS OR CORRECTIVE ACTIONS GSI/(WA No.-)
TITLE APPLICABILITY-STATUS
- CO M NTS-40 (8065)
Safety Concerns Associated With All 8WRs Pipe Breaks-'In The BWR Scram System flA 41 (8058)
BWR Scram Discharge Volume Systems' All BWRs NA 43 (8107)
Reliability Of Air Systems All Plants I/9-90 Attached 51 (L913)
Improving the Reliability-of All Plants
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I/12-91 Attached Open-Cycle Service Water Systems 67.3.3 (A017)
Improved Accident Monitoring All Plants C
Attached 75** (8076)
Item 1.1 - Post-Trip Review All Plants (Program Dercription and-Procedure)
C-Attached 75 (9085)'
~ Item 1.2 - Post-Trip' Review -
All Plants Cc Attached' Data and'Information Capability
- Please follow attached guidance for completing this-column.
- The 16-items listed for GSI 75 all. relate to actions derived from the generic'feplications of Sales AIWS even' a Item' numbers correspond to Generic Letter 83-28 action ites numbers..
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TITLE APPLICA8ILITY STATUS
- C0fGENTS 75_(8077)
Item 2.1 - Equipment Classi :
All. Plants.
fication and Vendor' Interface (Reactor Trip System Components)
C Attach.ed.
75 (8086)
. Item 2.2.1~- Equipment Classifi--
All Plants
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t cation for Safety-Related Components C
.75 (LOO 3)
Item 2.2.2 - Vender Interface All Plants
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for Safety-Related Components C'
Attached 75'(8078)
Items 3.1.1 & 3.1.2 - Post -
All Plants Maintenance Testing (neactor Trip System Components)
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Attached 75 (8079)
Item 3.1.3 - Post-Maintenance All Plants Testing-Changes to Test Require-4 ments (Reactor Trip System Components)
C Attached 75 (8087)
Items 3.2.1 & 3.2.2 - Post-All Plants
-Maintenance Testing (A11'Other Safety-Related r-,;_:..ts)
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Attached 75 (8088)
Item 3.2.3 Post-Maintenance
'All Plants-Testing-Changes to Test Require-ments (All Other. Safety-Related Components)
C-Attached 75 (2080)
Ites 4.1 - Reactee' Trip System Ali Plants Rellability (Vender-Related.-
C Attached' Modifications)
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- COBOEtITS; ~
75 (8081) Items 4.2.1 & 4.2.2 -~Reacteri All PWRs a Trip System Reliability-9taintenance and Testing-l .(Preventative plaintenance and-Survelliance Program for- -a Reactor Trip Breakers). 'I/12-91:
- Attached'
. 75'(8082) Itesl4.3 - Reactor. Trip System- .All W and 88W-Reliability' '.-Design flodifications Plants (Automatic Actuation of Shunt. Trip. Attachment for Westinpuouse'and 88W- -Plants) NA 75 (8090) Item.4.3 - Reactor Trip System-All W & 8&W Reliability - Tech Spec Changes-Plants (Automatic. Actuation of' Shunt Trip Attachment For Westinghouse' and 88W Plants). NA l 4 l 75 (8091) Item 4.4 - Reactor Trip System. All 88W Plants Reliability-(Improvements in-Maintenance.and Test Procedures i for 88W Plants) NA L i - t ... ~. - _-.l. ...:. ;. - ; s,- ~.i - e... - - a,, _ :. . ~... _ _ _ _ _,. ~ _. -
~ ~ ~ 3 z a m .g. -GSI/(W A No.} TITLE APPLICABILITY ~ . STATUS *
- C00DIENTSL 75 (8092) htes 4.5.1 - Reactor Trip System All Plants Reliability-Diverse Trip Features Attached C
(System Functional Testing). 75 (8093) Items.4.5.2 & 4.5.3 - Reactor Trip All Plants System Reliabilityc-Test'Alterna-tives and Intervals'(System-Attached Functional Testing) C 96 (8084) Long Range Plan for Dealing All BWRs witP. Stress Corrosion NA Cracking in BWR Piping 93 (8090) Steam Binding of Auxiliary All PWRs C Attached' Feedwater Pumps 99 (L817) RCS/RDWt Section Line. Valve All PWRs C-Attached . Interlock on PWRs 124 Auxiliary Feedwater System -ANO-1&2, Rancho Reliability Seco, Prairie NA Island 1&2, Crystal River-3 ft. Calhoun A-13 (8017) Snubbee Operability Assurance - All Plants C Attached; Hydraulic Snubbers
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- GSI/(IPA Ho.)
- TITLE:
APPLICA81LITY- ' STATUS
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A-13 (8022) Snubber Operability' Assurance:-- = All Plants- ~ L Mechanical Snubbers'- C' ' Attached' e A-16'(D012) . Steam Effects on BWR Core: Oyster Creek- . Spray Distribution &ler-1 NA .A-35 (8023) Adequacy of Offsite Power All Plants. Systems C Attached J l. 8-10 8ehavior of BWR Mark III All 8WR Mark III Containments Plants NA 8-36 Develop Design,-Testing and _ All Plants with Maintenance Criteria for OL Applications Atmosphere Cleanup System After 4/1/80 Air Filtration.and Adsorption Units for Engineered Safety' Features Systems and.for.. NA-Norinal Ventilation Systems [ ~i 8-63 (8045) Isolation of Low Pressure- -All Plants Systems Connected:to the Reactor Cociant System Pressure C. Attached Soundary' a .-a. g' L_.,.,y.~, ,,,.,y, ) ,,v.'..,....~_f.hy. ,,A._ye .,g' .,.,yj $ p, 4.,.,k..,,...,,,,,
J.- _,( # .yy ~ 7 t(/ Attachment to Guidance For Completina Status Column in Enclosure 1 (1) Provide'a separate entry for each licensed reactor unit. If the information is identical for multiple units, so state. '(2) If.a GSI is not applicable to a unit (s), enter "NA".- -(3). If a GSI is applicable but no changes were necessary to implement the resolution, enter "NC". If the GSI implementation was completed prior to 1 issuance of the operating license, enter "NC", as no post-licensing changes were necessary. '(4) If a GSI' is applicable', submittal of information and/or changes were I necessary and such submittals were made or changes are complete, enter "C". L; Also identify the licensee's document (s) to the NRC which certified . completion, and the document date(s). L (5) If.a GSI is applicable.and changes are necessary but such changes are not yet fully implemented, enter "I" and the projected month and year of completion.. Provide a brief explanation of the outstanding work in the J N " Comments" column. (6) If-implementation guidance for a resolved GSI was issued recently and the licensee is-still evaluating the appropriate response, enter "E" and .the projected response date. L (7)' The " Comments" column may be used to explain any entry in the " Status" L column. p i l l: I L F
~ ~ g y4 J; A MAINE YANKEE COMMENTS TO ENCLOSURE (1) 0F NRC GENERIC' LETTER 90-04' - fdl Comments (correspondence unless otherwise indicated) .43 Outstanding work to be reported includes:
- 1) Completion of instrument air quality testing
- 2) Vertical audit of maintenance practices, emergency procedures, and training 3)
Preparation of Instrument Air Design Basis document 4.. Vertical. audit of air system design and operating requirements 5 Testing of safety-related instrument air system. components N te: All. of-these items are-documented in Maine Yankee letter to the NRC. dated February 24,-1989. 51 Outstanding work to be reported includes:
- 1) Vertical audit of the service water system and evaluation of thermal backwash mussel control procedures.
- 2) Verify heat transfer capability of service water heat exchanger and modify.as necessary.
3) Evaluate component cooling system for extension of the service water test program to this system. 4) Evaluate current service water system inspection and maintenance- . programs.
- 5) Review service water and component cooling systems to ensure ability to perform their intended safety functions.
- 6) Conduct.walkdown inspection of both cooling systems.
- 7) Review maintenance practices,
- training, and operating and emergency procedures to ensure adequacy.
' Note: All of these items are documented in Maine Yankee ' letter to - the NRC dated January 29,~ 1990. 75 (B076) MY-NRC, 11-10-83 MY-NRC, 01-31-84 NRC-MY,'04-24-85 75 (B085) MY-NRC, 11-10-83 NRC-MY, 10-30-85 NRC-MY, 02-29-88 MY-NRC, 04-01 NRC-MY, 07-?S-88 75'(B077) MY-NRC,'11-10-83 MY-NRC, 02-04-84 NRC-MY, 04-19-85 MY-NRC; 06-18-85 NRC-MY, 05-21-87 NRC-MY, 07-29-87 SEN90182.LTR te e
t;; s 3 r,; y 3 .l; .i:n(i. -' t' i75L(8086)L . MY-NRC~ 11-10-63 NRC-MY, 04-19-85. NRC-MY, 06-04-87 m N /75L(L003) MY-NRC, 11-10-83 i a: NRC-MY, 04-19-85 o* - MY-NRC,.06-18-85 MY-NRC,L08-20-85 4 NRC-MY,.03-16, ,T. - L 75-(B078): MY-NRC,.11-30-83 i - MY-NRC, 02-01-84. -}i V "V NRC-MY, 05-27-86 75L(B079) MY-NRC, 11-10-83 NRC-MY,'04-19-85 j m NRC-MY, 10-21-85 E
- 75'(B087)
MY-NRC,-11-10-83 MY-NRC, 06-01-84 NRC-MY, 05-27-86 .t NRC-MY, 05-04-87 75;(8088) 'HY-NRC, 11-10-83 + NRC-MY, 04-19 ' NRC-MY, 10-21-85 ? 9 -75:(8080)L ~ MY-NRC, 11-10-83 NRC-MY, 05-27-86 1 1 1 i'
- 75 (8081)-
MY-NRC,,11-10-83. ' MY-NRC, 12-15-832 NRC-MY, 12-20-84 t MY-NRC, 01-25-85: - MY-NRC, 10-28-85
- j EX-MY, 01-31490 m
. 0utstanding work includes the installation and operation of the ATWS i equipment scheduled to be completed as indicated.' 3 l n J75-(B092)' MY-NRC, 11-10-83 MY-NRC, 12-15-83 NRC-MY, 04-19-85 NP.C-MY, 05-27 m ~l75 (8093)~ ~ MY-NRC,: 11-10 l f NRC-MY, 04-19-85 MY-NRC, 06-07-85'- i NRC-MY, $ 02-14->87 j i i 93: MY-NRC,,02-27 - MY-NRC,l05-23-88 I[i 4 lSEN90182.LTR / a } i i 4
[le!?T . fs: S-1 sag ' f ; i s MAINE YANKEE COMMENTS TO 5 ENCLOSURE (1) 0F NRC GENERIC LETTER 90-04 (Continued) 99-MY-NRC, 01-12-89 MY-NRC, 02-02-89 I ae, NRC-MY,.05-15-89; <1 A-13; MY-NRC, 04-03-81 NRC-MY, 09-14 -l -MY-NRC, 10-28-82 75 MY-NRC, 01-17-83~ i NRC-MY, 09-01-83 i MY-NRC,=02-29-84 1MY-NRC,- 04-10-84 i ~MY-NRC, 09-12-85 MY-NRC, 01-30-86 .l MY-NRC, 08-14-86 l NRC-MY, 04-03-87' l NRC-MY, 08-18-87 -i 2 'A 35 MY-NRC, 09-14-79 o .MY-NRC, 02-29-80 { .B-63 .MY-NRC, 03-13-80 MY-NRC, 03-09-81 MY-NRC,.06-03-81 MY-NRC, 06-30-81 MY-NRC, "?-06-81 'l NRC-MY,;07-10-81 1 I- .- l i i SEN90182.LTR ,}}