ML20034C510
| ML20034C510 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/26/1990 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-CR-5488 C311-90-2052, NUDOCS 9005040053 | |
| Download: ML20034C510 (3) | |
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-3' GPU Nuclear Corporation gy..t; gg One Upper Pond Road.
Parsippanyi New Jersey 07054 201 316-7000 TELEX 136-482
- Writer's Direct Dial Number:
C311-90-2052-April 26, 1990 U. S.' Nuclear Regulatory Commission
. Attn: Document Control Desk k
Washington, DC 20555 Dear-Sir-Three Mile Island Nuclear Generating Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No.:50-289 Comments on Risk-Based Inspection Guide for Three Mile Island,' Unit 1-NRC letter dated February 9, 1990 (C311-90-3033) transmitted a draft Risk Based-Inspection Guide for THI-l (NUREG/CR-5488, November 1989)-and requested.GPUN-technical comments or suggestions on the~ draft.
Enclosed is a tabulation of CPUN comments on the draft Risk Inspection Guide (RIG). We understand the RIG-will be finalized with any necessary corrections and' issued.for use at'THI-1.-
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Sincerely,
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%H.D.Hukill
~1 HDH/DJD/lt Enclosure Vice President and Director, TMI-l cca J.
- Stolz, USNRC R. Hernan, USNRC T. Martin, USNRC, Region I F. Young, USNRC, THI-l 900504'0033 900426 DR ADOCK 05000289 PDC f
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' GPU Nuclear Corporation is a subsidiary of General Public Utilit:ss Corporation
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C3al-90-2052 Sheet 1 of 2 ENCLOSURE glyE_92mments on Draft Risk Inspection Guide (NUREG/CR-5488.' November 1989) 1.
Page 5.3, operator action #7 revise words "for injection" to "for RCP peal injection", for proper clarification.
2.
Figure A1.1, page A.7 revise valve tag nos. "MU-V-7A, MU-V-7B" to
- 1AD "DH-V-7A, DH-V-7B", respectively.
3.
The following valve positions on various Figures should be revised as noted below to denote normal valve lineups:
Floure Chanae ZI25 22 A1.1 DH-V-4A Open-Closed A1.1 DH-V-4B.
Open Closed A2.1 MU-V-69A Open Closed A2.1 MU-V-69B Open Closed AS.2 Complete lineup shows system isolated and shutdown which is not the normal condition.*
A6.1 All valves are shown open which is not the normal condition.*
A7.1 EF-V-30 A,B,C,D Open
-Closed A7.1 EF-V-8'A,B,C Closed Open A7.2 System has been modified.*
A10.1 System-has been modified
- A14.1 BS-V-3A Open Closed A14.1 BS-V-3B Open Closed A14.1 The lines labeled "From Sodium Hydroxide Tank" are actually from the deleted Sodium Thiosulfate Tank.
Revise wording "From Sodium Hydroxide Tank" to "From Deleted Sodium Thiosulfate Tank".
Note
- Reference latest FSAR Figure for correct valve lineups or latest system configuration.
4.
Page A.10, Item 13: delete the words "in series". The check valves referred to are not all in series in one single flow path.
5.
Figure A3.1: change "DC-V-5A" to "DC-V-65A".
6.
Page A.47, Item 7:
The failure mode for the listed valves should be revised from " failure to open" to " failure to remain open".
7.
Page B.8, Table'A9-1, Item'7: Revice failure mode description from
" Failure of Motor-Operated Valves to open" to " Failure of Motor-Operated Valves to Remain Open".
8.
Page D 2, Table D-1:
Either delete "X"
for Instrument Air to Reactor Building Isolation, or add a note to clarify that instrument air loss deca not cause failure of the Reactor Building to leolate.
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-C311-90-2052; Sheet 2 of 2 9.
Page A.1, Section A.1's Delete the word " training" from codes PC, PT, and MT.
Inspection activities.should focusDon procedures and actual.
performance of maintenance activities. Training may be evaluated'if a job deficiency is observed.in the, field, but training should not be-a primary inspection activity. This is consistent with Page B.1,-
Sections B.2 and B.3 which do not include any-reference to training.
10 Page A.59, Table A12-1, Item 2: Delete the code "OP" from this item ~
since this is not an operator task.-
'll.;Page=A.64,. Table A13-1,. Item'l&2:
Delete the. codes."(MT,PT, OP)"
from both. activities, Reactor Building Purge and Sump-Draining, since no specific failure mode is assumed.'
- 12. Page B.3,'
Table'Bli Delete "ESAS Sensors Calibration Table A12-1,.
. Item 2" since this is not an operator. task.' Delete " Reactor Building Purge in Progress Table A13-1, Item-1" since this is not a human error as described in the heading.= Delete," Sump Draining in Progress
, Table A13-1,-Item 2" since this is not a: human errorlas described-in the heading.
13 _Page 2.1, Last sentence of paragraph #2:
Delete the following.
sentence: "These revisions to the PRA have not yet been performed."
Substitute the following sentences."GPUN has revised'the PRA model as reported in a letter dated March 17,.1989, but the'PRA report will j
lnot be revised until completion of the IPE."
- 14. Page 2.3,.Section 2.1.2, Description of the Loss of River Water Scenario should also identify thatoan RCP seal LOCA could occur due to the loss of seal injection flow and loss of thermal barrier cooling.
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