ML20043H524
| ML20043H524 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/18/1990 |
| From: | Nichols S Maine Yankee |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-90-04, GL-90-4, MN-90-61, SEN-90-182, NUDOCS 9006260056 | |
| Download: ML20043H524 (10) | |
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i MaineYankee 8E6 atti (LICvoofv eCA Wamt WCf '9P2
. EolsON oAlvE AUGUSTA MAINE 04330. i2on 622 4868 IN0TEi Due to-page : omissions, please substitute this letter for one previous'ly received.
l June 18, 1990 MN-90-61 SEN 90-182 1
UNITED STATES NUCLEAR REGULATORY COMMISSION Attention: D6cument2 Control Desk i
- Washington, DC,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 W'1 Imposition of Requirements or Corrective Actions (Generic-LScter 90-04) iubject: Response.to Generic letter 90-04, Implementation of Generic Safety Issues (GSI) Requirements-t Gentlemen:
Maine Yankee has reviewed the status of implementation of Generic Safety Issues, as requested' and identified in Reference (b).
Attached is an annotated copy of j
. Enclosure (1) of Reference (b). We have marked the attachment with our judgement of status based on a review of uur records for each item as applicable to Maine Yankee.
This status report.is not intended to make any commitments for Maine Yankee or modify any previous commitments. Also, please note the attachment provides1 expected dates j
of. implementation-fer. several pending items.
Maine Yankee considers these dates i
tentative based on our current plans.
Should you have any questions on the attached, please contact me.
Very truly yours, j
M4lt 1
S. E. Nichols Licensing Section Head SEN:SJJ Attachment (Annotated-Enclosure (1) of Generic letter 90-04) c:
Mr. Thomas.T. Martin 7
4 Mr. Eric J. Leeds
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Mr. Richard J. Freudenberger l }
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b ATTACHMENT
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Annotated Copy of Enclosure (1) of NRC Generic Letter 90-04
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i FACILITY N M :- Maine Yankee Atomic Power. Company-l i
~ DOCKET NO.:
50-309 l
LICENSEEi-
.Haine-Yankee Atomic Power Company l
STATUS OF LICENSEE IW LEnENTATION OF GENERIC SAFETY ISSUES RESOLVED WITN IMOSITION OF REQUIRENENTS OR CORRECTIVE ACTIONS 1.
GSI/(WA No.)
TITLE APPLICA8ILITY STATUS
- CO M NTS-40~(8065)
Safety Concerns Associated With All BWRs l
Pipe Breaks In The BWR Scram System NA 5
41 (8058)
BWR Scram Discharge Voltane Systems All BWRs NA
'43 (8107)
Reliability Of Air Systems All Plants I/9-90 Attached 51 (1.913)
Improving the Reliability of All Plants Open-Cycle' Service water Systems I/12-91 Attached i
67.3.3 (A017)
Improved Accident Monitoring All Plants C
Attached 75** (8076)
Itear 1.1 - Post-Trip Review A11 Plants l
(Program Description and
-Procedure)
C Attached-75 (8085)
Item 1.2 - Post-Trip Review -
All Plants Data and.Information Capab.ility C.
Attached j
f-Pieasefollowattachedguidanceforcompletingthhscolumn.
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"*The 16 items listed for GSI 75 all relate to actions derived from the generic implications of
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Salem ATNS events.
Item numbers correspond.to Generic Letter 83-28 action item numbers.
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GSI/(WA No.)
-TITLE-APPLICABILITY STATUS
- CO M NTS
' 75 (8077)
Item 2.1 - Equipment Classi-All Plants fication and Vendor Interface.
'(Reactor Trip. System Components)-
C Attached'
- 75 (8086)
. Item 2.2.1 - Equipment Classiff-All Plants a
cat. ion for Safety-Related Components C
Attached 75 (LOO 3)
Item 2.2.2 -' Vendor Interface All. Plants i
for Safety-Related Components C
Attached.
75 (8078)
Items 3.1.1 & 3.1.2 - Post -
All Plants Maintenance Testing (Reactor
+
Trip System Components)
C Attached 75 (8079)
Item 3.1.3 - Post-M11ntenance All Plants Testing-Changes to iest Require-ments (Reactor Trip System Attached 1
C Components) l 75 (8087)
Items 3.2.1 & 3.2.2 - Post-All Plants Maintenance Testing (All Other.
Safety-Related Components).
C' Attached 75 (8088)
Item 3.2.3
~ Post-Maintenance -
All Plants Testing-Changes to Test Require-ments (All Other-Safety-Related
- Attached-I Components)
C 75 (E080)
.Ite 4.1 - Reactor Trip System Ali Plants i
Reliability (Vender-Related Attached
-Modifications)
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GSI/(frA No.)
' TITLE APPLICABILITY STATUS
- COMIITS
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75 (8081)
Items 4.2.1 & 4.2.2 - Reactor All PWRs Trfp System Reliability--
plaintenance and Testing l
. (Preventative plaintenance and i
Survel11ance Program'for Reactor Trip Breakers)
I/12-91 Attached.
75 (8082)
Ites 4.~3 - Reactor Trip System All W and 88W
- Reliability. Design flodifications -
Plants (Automatic Actuation of Shunt Trip Attachment for idestinpuouse and 88W Plants)
NA i
75 (8090)
Item 4.3 Reactor Trip System.
All W & 88W l
Reliability - Tech Spec Changes Plants (Automatic Actuation of Shunt Trip Attachment For idestinghouse f
and 88W Plants)
NA
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75 (8091)
Item 4.4 - Reactor Trip System All 88W Plants f
Reliability-(Improvements in l
lflaintenance and Test Procedures t
for 88W Plants)
NA i
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TITLE APPLICA8ILITY STATUS *'
C0f9EENTS 75 (8092)
.Ites 4.5;1 - Reactor Trip System.
AICPlants.
. Reliability-Diverse Trip Features
'(Systes Functional Testing)
C Attached' 75 (8093)
Items 4.5.2 & 4.5.3 - Reactor Trip All Plants l
Systes Reliability - Test Alterna-tives and Intervals.(Systee Functional Testing)
C Attached 86 (8084)
Long Range Plan for Dealing ~
All BWRs with Stress Corrosion Cracking in SWR Piping NA I
93 (8098)
Steae Binding of Auxiliary All PWRs Feedwater Pumps C
-Attached 99 (L817)
RCS/RNR Suction Line Valve All PWRs Interlock on PWRs.
C Attached 124 Auxiliary Feedwater System ANO-1&2, Rancho Reliability-Seco, Prairie NA Island 1&2, Crystal River-3 Ft. Calhoun
[
A-13 (8017)
Snubber Operability Assurance -
All-Plants Hydraulic Snubbers C
Attached i
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TITLE-APPLICABILITY STATUS
- CepgesTS
-A-33 (8022)
Snubber Operabliity Assurance -
All Plants flechanical Snubbers C
Attached A-16 (0012)
- Steam Effects on SWR Core Oyster Creek NA Spray Distribution
& 18eP A-35 (8023)
Adequacy of offsite Pouer All Plants C
Attached Systems-
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B-10 Behavior of BWR 90erk III All 9WR Mark III NA Containments Plants B-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 llorsal Ventilation Systems
- NA 8-63 (8045)
Isolation of Low Pressure All Plants Systems Connected to the Reactor Coolant System Pressure C
Attached Boundary
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-MAINE YANKEE COMMENTS TO ENCLOSURE (1) 0F NRC GENERIC LETTER 90-04 Sil 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
-Note:
All of these items ar; documented in Maine Yankee letter to' the NRC dated February 24,.*.989.
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,'04-01-88 (f -
NRC-MY, 07-26-88 75 (B077)
MY-NRC,'11-10-83 MY-NRC,'02-04 NRC-MY, 04-19-85 MY-NRC,'06-18-85 NRC-MY, 05-21-87 NRC-MY, 07-29-87 SEN90182.LTR i
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L75L(B086)
MY-NRC,:ll-10-83 1
.NRC-MY, 04-19-85 NRC-MY, 06-04-87 p'
-75 (LOO 3)-
.MY-NRC, 11-10-83 l
L' NRC-MY, 04-19 "
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.MY-NRC, 06-18-85 MY-NRC, 08-20-85 NRC-MY, 03-16-88 75-(B078)
MY-NRC, 11-10-83 MY-NRC,.02-01-84 NRC-MY, 05-27-86' 75 (8079)
MY-NRC, 11-10 -
'NRC-MY, 04-19-85 NRC-MY, 10-21-85 75'(B087)
MY-NRC, 11-10-83 j
MY-NRC, 06-01-84 NRC-MY, 05-27-86 o
NRC-MY, 05-04-87
-75 (B088)
MY-NRC, 11-10-83 NRC-MY, 04-19-85 NRC-MY, 10-21-85 75 (8080)
MY-NRC, 11-10-83
~NRC-MY, 05-27-86 75 (8081)
_MY-NRC,.11-10-83 MY-NRC, 12-15-83 NRC-MY, 12-20-84 MY-NRC, 01-25-85 MY-NRC, 10-28-85~
NRC-MY, 01-31-90 a
t Outstanding work includes the installation-and operation of the ATWS equipment scheduled to be completed as indicated.
75-(8092)
MY-NRC, 11-10-83 MY-NRC, 12-15-83 NRC-MY, 04-19-85 NRC-MY,-05-27-86 75 (B093)
MY-NRC, 11-10-83 NRC-MY, 04-19-85
.MY-NRC, 06-07-85 NRC-MY, 02-14-87.
93 MY-NRC, 02-27-86 MY-NRC, 05-23-88
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MAINE YANKEE COMMENTS TO ENCLOSURE (1) 0F NRC GENERIC LETTER 90-04 (Continued) 99.
- MY-NRC, 01-12-89 MY-NRC, 02-02-89 NRC-MY, 05-15-89
[A-13 MY-NRC, 04-03-81 NRC-MY, 09-14-82 MY-NRC, 10-28-82 i
- MY-NRC, 01-17-83 NRC-MY, 09-01-83 MY-NRC, 02-29-84 MY-NRC,.04-10-84 MY-NRC, 09-12-85 MY-NRC, 01-30-86 MY-NRC, 08-14-86' NRC-MY, 04-03-87
'NRC-NY,.08-18-87 A-35'-
MY-NRC, 09-14-79 i
MY-NRC, 02-29-80
'B-63 MY-NRC,-03-13-80 e
MY-NRC, 03-09-81 MY-NRC, 06-03-81 MY-NRC, 06-30-81
- MY-NRC, 07-06.
NRC-MY, 07-10-81 n
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