ML20129A588
| ML20129A588 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/17/1996 |
| From: | Terry C, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20129A594 | List: |
| References | |
| TXX-96489, NUDOCS 9610220191 | |
| Download: ML20129A588 (5) | |
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Log # TXX 96489 File # 10010.1
-r 905.4 Ref. # 10CFR50.55a(f)
October 17, 1996 C. Lance Terry Groep Vke PresMent i
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 4
SUBJECT:
C0HANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50 445 AND 50 446 UNIT 1/ UNIT 2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES, REVISION 7 (1989 EDITION OF ASME CODE. SECTION IX, NO ADDENDA:
UNIT 1 INTERVAL START DATE: AUGUST 13, 1990 FIRST INTERVAL:
UNIT 2 INTERVAL START DATE: AUGUST 3, 1993 FIRST INTERVAL)
Gentlemen:
Enclosed is Revision 7 to the Comanche Peak Steam Electric Station (CPSES)
Unit 1 and 2 Inservice Testing Plan (IST) for Pumps and Valves in the j
first interval. The Plan is a combined Unit 1/ Unit 2 Plan, implementing the same requirements from che ASME Boiler and Pressure Vessel Code,Section XI,1989 Edition of Section XI (No Addenda) on Units 1 and 2.
The 1
effective date of this revision was October 16, 1996, at 9:01 PM CST.
The attachment provides a detailed deccription of the changes made by Revision 7 to the Plan in a format itical to that provided for changes to the Final Safety Analysis Report rSAR). All changes described in the i
attachment have been evaluated for relative significance (i.e., the group number 1, 2, 3 or 4 corresponds to each change justification as discussed in TU Electric letter TXX 88467 dated June 1, 1988).
In addition, all changes applicable to CPSES Units 1 and 2 have been reviewed under the TU Electric 10CFR50.59 process and found not to include any "unreviewed i
safety questions."
This transmittal does not contain a request for relief from ASME Code Requirements and is provided to update your manual.
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9610220191 961017 PDR ADOCK 05000445 f
r PDR 220Un 1
P.O. Uux 1002 Olen Rose. Texas 76043
TXX 96489 Page 2 of 2 If you have any questions, please call Mr. Carl Corbin at (817) 897-0121.
Sincerely, C. Lance Terry By:
aC6f RogeVD. Walker Regulatory Affairs Manager CBC Attachment Enclosure c-Mr. L. J. Callan, Region IV Mr. J. I. Tapia, Revion IV Resident Inspectors, CPSES Mr. T. J. Polich, NRR Mr. G. Bynog, TDLR (clo)
Mr. J. C. Hair. Authorized Nuclear Inservice Inspector Mj l
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Attachment to 'lXX-96489 CPSES -INSERVICE TEST PROGRAM AMENDMENT-7 DETAILED DESCRIPTION Prefix Page Page 1 (as = mended) fung Descrintinn TABLE 13-2 Fevise the method of testing for check valves 1-8956A, B, C, & D (pages 15
& 16) from partial disassembly and inspection to flow testing and nonintrusive techniques. 'the change will be implemented during the fifth i
refueling outage for Unit 1. Note 8 (page 20) of Table 13, " Safety injection,"
will be revised accordingly.
a Revision i
These valves are currently tested by disassembly and inspection in accordance with note 8 of Table 13 and Relief Request V7.
Procedures have been developed to implement flow testing and nonintrusive techniques during the fifth refueling outage fo-Unit 1. The new flow testing and nonintrusive techniques described in the change are consistent with the guidance in Section 4.1.2, " Exercising CheckValves with Flow and Nonintrusive Techniques," of NUREG 1482, " Guidelines for Inservice Testing at Nuclear Power Plants." Use of the flow testing and nonintrusive techniques does not require relief from the ASME Code because this method is considered "other positive means" of verifying disk movement.
4 The new test methods become effective for the Unit i valves during the fifth refueling outage for Unit 1.
Relief Request V7 and the related discussion in the Note 8 reraain valid for
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the Unit 2 valves. TU Electric anticipates implementing a similar change for
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i the Unit 2 valves in a future Unit 2 refueling outage.
Change Request Number IT 4. 1 l
Related SER : 3.9.6 SSER : 26 App R SER/SSER Impact N
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i ENCLOSURE TO TXX 96489 4
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COMANCHE PEAX STEAM ELECTRIC STATION UNITS 1 & 2 INSERVICE TESTING PLAN (IST)
INSTRUCTION SHEET (Page 1 of 1)
The following instructional information and checklist is being furnished to help insert Revision 7 into the Comanche Peak Steam Electric Station IST.
Discard the old sheets and insert the new sheets, as listed below.
i' Remove Insert Cover Sheet Cover Sheet Table 13 Page 1 of 17 Page 1 of 21 Page 2 of 17 Page 2 i
Page 3 of 17 Page 3 Page 4 of 17 Page 4 Page 5 of 17 Page 5 Page 6 of 17 Page 6 Page 7 of 17 Page 7 Page 8 of 17 Page 8 Page 9 of 17 Page 9 Page 10 of 17 Page 10 Page 11 of 17 Page 11 Page 12 of 17 Page 12 Page 13 of 17 Page 13 Page 14 of 17 Page 14
{
Page 15 of 17 Page 15 4
Page 16 of 17 Page 16 Page 17 of 17 Page 17 Notes, Page 1 Page 18 Notes, Page 2 Page 19 Notes, Page 3 Page 20 Notes. Page 4 Page 21 4
List of Effective Paaes EPL 1 through EPL 5 EPL 1 through EPL 5 i
NOTE: Please complete the entry for insertion of Revision 7 on the " Record of Changes" form located at the beginning of the IST Plan.
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October 16, 1996
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