ML20043H403
| ML20043H403 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/18/1990 |
| From: | Long R GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR C311-90-2080, GL-88-14, GL-89-13, GL-90-03, GL-90-04, GL-90-3, GL-90-4, NUDOCS 9006250364 | |
| Download: ML20043H403 (7) | |
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OPU Nuclear Corporation
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Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number
- June 18, 1990 C311-90-2080 U.;S.. Nuclear Regulatory Commission LAttn: = Document Control Desk 1
Washington,=DC--20555 3:
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Dear Sir:
?
Three Mile, Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 t
Docket No. 50-289 GPUN Response to Generic Letter (GL) 90-04 g,
" Request for Information on the Status of Licensee
(
Implementation of Generic Safety Issue Resolved' with Imposition of Requirements or Corrective Actions"'
1, GL 90-04 requests that'GPUN review and provide documentation =of the current implementation status of all. generic safety issues i
.(GSIs) identified therein that apply to TMI-1.,
1 provides GPUN's completion of the tabular-'information'given.in-
' ' 'm :toithe generic letter.
s LThe implementation status.for GSI-requirements given in k indicates, to-the.best of.our. knowledge, when the implementation of GSI requirements was completed or is expected O
- to be complete.
I Sincerely, j
l':
U R. L. Long n
i, Vice President nd Director, 1
ibi corporate Services-3 7
Attachment i
RLL/RDW l
l' cc:
J.
Stolz R. Hernan l '-
F.' Young I
L T. Martin d
9006250364 900616 PDR ADOCK 03000289 P
PDC GPU Nuclear Corporation is a subsidiary of Genera; Pubhc Utilities Corporation L- -
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FACILITY NAMEi TMI-1
. Attachment 1
~~
DOCKET:NO.:
'50-289
~
LICENSEE:
GPU' Nuclear Corporation
^
STATUS OF LICENSEE IMPLEMENTATION OF GENERIC' SAFETY ISSUES RESOLVED WITH~ IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS GSI/(MPA No.)
TITLE APPLICABILITY STATUS $
COMMENTS 40 (B065)
Safety Concerns Associated With All BWRs N/A
'This item does not apply to Pipe Breaks In The BWR Scram PWRs System 41 (BOSS)
BWR Scram Discharge Volume Systems All BWRs N/A This item does not apply.to PWRs 43 (B107)
Reliability of Air Systems All Plants I
Modifications have been performed to improve the-Instrument Air System reliability per the actions-required by GL 88-14. An additional air compressor is also being installed. Fu)1 implementation is expected to be achieved by the end of the 9R refueling. outage (currently -
scheduled for the 4th qtr.
1990). Refer to letter C311-89-3086 dated March 29, 1989.
51 (L913)
Improving the Reliability of All Plants I
Expected Completion.date is l
Open-Cycle Service Water Systems end of the 9R' refueling outage (Reference GPU Nuclear Letter.
0311-89-2115 dated January 26,1990). Item will be j
complete following the implementation of Recommended l
Action IV in GL 89-13 l
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I Attachmeht 1'.
GSI/(MPA NO.)
TITLE APPLICABILITY STATUS
- COMMENTS 67.3.3 (A017) Improved Accident Monitoring All Plants 03/90 C Completion of 8R refueling.
outage mod to add computer recording capability.
-5211-87-2103, dated-05/27/87; and C311-88-3162 dated ' 7/15/88 75 (B076)
Item 1.1 - Post-Trip Review All Plants 00/84 C 5211-83-2330, dated 11/08/83 ~
(Program Description and Procedures Revised (AP 1063)'
Procedure) 75 (B085)
Item 1.2 - Post-Trip Review -
All Plants 00/84 C AP 1063, Rev 0,'06/84 Data and Information Capability 5211-83-2330, dated 11/08/83 5211-86-3154, dated 06/12/86 (SER) 75 (B077)
Item 2.1 - Equipment Classi-All Plants 05/87 C 5211-87-2099, dated 05/29/87 fication and Vendor Interface 5211-87-3255, dated 12/10/87 (Reactor Trip System Compcnents)-
(SER) 75 (B086)
Item 2.2.1 - Equipment Classifi-All Plants 01/88 C Procedure update based on cation for Safety-Related vendor manuals.
Components 5211-87-2099, dated 05/29/87
.5211-87-3243, dated 11/18/87 (SER) 75 (LOO 3)
Item 2.2.2'- Vendor Interface for All Plants 09/90 E Response to GL 90-03 due to Safety-Related Components NRC 09/20/90 75 (B078)
Items 3.1.1'& 3.1.2' Post -
All Plants 01/88 C Procedure update based on Maintenance Testing.(Reactor Trip vendor manuals System components) 5211-83-2330, dated'11/08/83; 5211-85-3252, dated 10/28/85 (SER)
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..Attachmeht li GSI/(MPA NO.)
TITLE APPLICABILITY STATUS
- COMMENTS
~
75.(B079)
Item 3.1.3 - Post-Maintenance All Plants 11/83 C 5211-83-2330, dated 11/08/83 Testing-Changes to Test Require-5211-85-3204, dated 08/05/85 ments (Reactor Trip System Components) 75 (B087)
Items 3.2.1 & 3.2.2 - Post-All Plants 01/88 C Procedure update based on Maintenance Testing (All Other vendor manuals.
Safety-Related Components)-
5211-83-2330, dated 11/08/83 5211-85-3252, dated 10/28/85 (SER) 75 (B088)
Item 3.2.3 - Post-Maintenance All Plants 11/83 C 5211-83-2330, dated 11/08/83 Testing-Changes to Test Require-ments_(All Other Safety-Related Components) 75 (B080)
Item 4.1 --Reactor Trip System All Plants 11/83 C 5211-83-2330, dated 11/08/83 Reliability (Vendor-Related 5211-85-3252, dated 10/28/85, Modifications)
(SER) 75 (B081)
Items 4.2.1 &'4.2.2 - Reactor Trip All PWRs 02/86 C 5211-86-2012, dated 02/10/S6 System Reliability.- Maintenance 5211-85-3303, dated 12/12/85 and Testing (Preventive (SER)
Maintenance and Surveillance Program for Reactor Trip Breakers) l 75 (B082)
Item'4.3 - Reactor Trip System All W and 00/84 C Completion of mod.(B/A 412408)
Reliability - Design Modifications B&W Plants 5211-85-2053, dated 05/20/85
. [
(Automatic Actuation of Shunt. Trip (50.59 ltr) ; 5211-84-3366, i
Attachment for~ Westinghouse and dated 10/31/84 (License B&W Plants)
Amendment 102) 75 (B090)
Item 4.3 - Reactor' Trip System All W and-10/84 C 5211-84-3366, dated 10/31/84 Reliability.- Tech Spec Changes B&W Plants (License Amendment 102)
(Autor**ic Actuation of Shunt Trip Attac + t for Westinghouse and
'B&W Plaa.
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. MtachmentJ GSI/(MPA NO.)
TITLE APPLICABILITY STATUS
- COMMENTS 75 (B091)
' Item 4.4 - Reactor Trip System All.B&W 11/83 C 5211-83-2330, dated 11/08/83 Reliability (Improvements in Plants Maintenance and Test Procedures for B&W Plants) 4 75 (B092)
Item 4.5.1 - Reactor Trip System All Plants 00/84 C SP 1303-4.1 Revised Reliability - Diverse' Trip Features (System Functional Testing) 75 (B093)
Items 4.5.2 & 4.5.3 - Reactor Trip All Plants 07/88 C 5211-83-2330, dated 11/08/83; System Reliability
_ Test Alterna-5211-85-2135, dated 08/23/85; tives and Intervals (System Functional Testing) 86 (B084)
Long Range Plan for Dealing with All BWRs N/A This item does not apply to Stress Corrosion Cracking in BWR PWRs Piping 93 (B098)
Steam Binding of Auxiliary All PWRs 07/88 C C311-88-2053, dated 05/16/88; Feedwater Pumps-1106-6, Rev 42, Effective 1/20/86; and operator training upgrade ECMP 88-102 completed 7/88.
99 (L817)
RCS/RHR Suction Line Valve All PWRs 12/91 I 9R refueling outage mod -
additional RCS shutdown level-Interlock on PWRs monitoring (412589) 124 Auxiliary Feedwater System ANO-1&2, N/A This item does not apply to Reliability Rancho Seco, TMI-1 Prairie
~ Island 1&2,
-Crystal River-3, Ft. Calhoun
,.4, Attachment 1..
.r GSI/(MPA NO.)'
TITLE LAPPLICABILITY STATUS
- COMMENTS A-13 (B017)
Snubber Operability Assurance -'
All Plants 09/85 C 5211-85-3085, dated 03/21/85 Hydraulic Snubbers (License Amendment 106) &
5211-85-3227, dated 09/09/85-(License' Amendment 110)
A-13 (B022)-
Snubber Operability Assurance -
All Plants N/A TMI-1 does not have mechanical.
Mechanical Snubbers snubbers A-16 (D012)
Steam Effects on BWR Core Spray.
Oyster Creek N/A This' issue did not apply to Distribution
& NMP-1 PWRs.
A-35 (B023)
Adequacy of Offsite' Power Systems All Plants 01/82 C Completion of undervoltage modification (1/25/82)
B-10 Behavior of BWR Mark III All BWR Mark N/A
-This issue did not apply to Containments III Plants PWRs.
B-36 Develop Design, Testing and All Plants N/A TMI-1 License was granted Maintenance Criteria.for with OL prior to 4/1/80.
Atmosphere Cleanup System Air Applications Filtration and' Adsorption Units After 4/1/80 for Engineered Safety Features t
Systems and for Normal Ventilation Systems B-63 (B045)
Isolation of Low Pressure Systems All Plants 03/80 C TLL 137, dated 03/31/80 Connected to the Reactor Coolant system Pressure Boundary i
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- iAttachment"1.
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' GSI/(MPA NO.)
TITLEc
- APPLICABILITY STATUS *'
COMMENTS
- C - COMPLETE NC - NO CHANGES NECESSARY NA
,NOT' APPLICABLE I - INCOMPLETE E - EVALUATING ACTIONS REQUIRED Note:
Items that are complete are preceded _by month and year of completion.
Those-' items.whose completion date:is-indicated by 00/XX indicates that the item was completed sometime during that year.
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