ML20141F832
| ML20141F832 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/26/1997 |
| From: | John Marshall TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20141F835 | List: |
| References | |
| TXX-97135, NUDOCS 9707030193 | |
| Download: ML20141F832 (6) | |
Text
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Log # TXX 97135
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Ref. # 10CFR50.55a(f) 1UELECTRIC'
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June 26, 1997 C. Lance Terry Gmup Mce Pressden l
i U. S. Nuclear Regulatory Commission Attention: Document Control Desk j
Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50 445 AND 50 446 UNIT 1/ UNIT 2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES, REVISION 9 (1989 EDITION OF ASME CODE, SECTION IX, NO ADDENDA:
UNIT 1 INTERVAL START DATE:
AUGUST 13. 1990 FIRST INTERVAL:
UNIT 2 INTERVAL START DATE:
4 AUGUST 3. 1993, FIRST INTERVAL)
Gentlemen:
Enclosed is Revision 9 to the Comanche Peak Steam Electric Station (CPSES)
Unit 1 and 2 Inservice Testing Plan (IST) for Pumps and Valves in the first interval. The Plan is a combined Unit 1/ Unit 2 Plan, implementing i
the same requirements from the ASME Boiler and Pressure Vessel Code.
Section XI, 1989 Edition of Section XI (No Addenda) on Units 1 and 2.
The i
effective date of this revision was June 26, 1997, at 11:00 PM CST.
l The Attachment provides a detailed description of the changes made by Revision 9 to the Plan in a format identical to that provided for changes to the Final Safety Analysis Report (FSAR). All changes described in the attachment have been evaluated for relative significance (i.e., the group 1
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 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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97Of036193 970626 PDR ADOCK 05000445 P
PDR P. O. Box 1002 Glen Rose Texas 7600
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TXX 97135 Page 2 of 2 If you have any questions, please call Mr. Carl Corbin at (817) 897 0121.
Sincerely, C. Lance Terry d'
By:
J. S. Marshall Generic Licensing Manager CBC/cbc Attachment Enclosure c-Mr. E. W. Herschoff, Region IV Mr. J. I. Tapia, Revion IV Mr. T. J. Polich, NRR Resident Inspectors, CPSES Mr. G. Bynog..TDLR (clo)
Mr. J. C. Hair, Authorized Nuclear Inservice Inspector
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REVISION - 9 DETAILED DESCRIPTION Prefix Page Page 1 (as amended)
Group Description TABLE 9-2 Page 3
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Adds main steam block valves (MS-0101 and MS-0128) to Table 9, " Main Steam"
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Addition The Main Steam valves IIV 2452-1 and HV 2452-2, supply steam from Steam Generators I and 4 to the Auxiliary Feedwater Pump Turbine. These i
valves utilize safety related air accumulators to maintain the valves closed during off-normal plant conditions. After exhausting the air accumulators, a secondary method of ensuring Containment Isolation is required. The upstream block valves (MS-0101 and MS-0128) fulfill this requirement.
The air accumulators supply safety related air to the air-operated valves upon loss of the non-safety related plant instrument air system.110 wever, by i
design, the air accumu ators only provide sufficient air to close the valves
-. __..-----ed-kap 4hm.-claedfor 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> withn ad<titional half hour allocated for
_ _g manual operator action. The block valves upstream ofIIV-2452-1,-2 are ASME Safety Class 2 gate valves with manual gear operators and have been qualified to function as secondary outside Containment isolation for penetrations Mi-0001 and Mi-0004.
The FSAR (LDCR-S.A-96-131) and Technical Requirements Manual (LDCR TR-97-007) are also being revised to be consistent with this change.
Change Request Number IT 6. 1 Related SER : 3.9.6 SSER SER/SSER 1mpact N
TABLE 13-2 Pages 15,16,22 Revise the method of testing for check valves 2-8956A, B, C, & D (pages 15
& 16) from partial disassembly and inspection to flow testing and nonintrusive techniques. The change will be implemented during the third refueling outage for Unit 2. Note 8 (page 22) of Table 13, " Safety injection,"
will be revised accoMingly.
Revision 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 nonintnnive techniques during the fifth refueling outage for 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 l
' Attachment to TXX 97135 i
i CPSES -INSERVICE TEST PROGRAM i
REVISION-9 DETAILED DESCRIPTION Prefix Page Page 2
@ amended)
Group Description is considered "other positive means" of verifying disk movement.
i The new test methods became effective for the Unit i valves during the fifth refueling outage for Unit 1.
Change Request Number IT 5. 1
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Related SER : 3.9.6 SSER 26 3.9.6 l,
SER/SSER Impact N
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A-19 2
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Updates the implementation status of Relief Request V-7 in Appendix A.
Adds a note stating "Beginning with the fifth refueling outage for Unit I and the third refueling outage for Unit 2, this relief request will no longer be used."
Revision
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has been revised from partial diassembly and inspection to flow testing and nonintrusive techniques. Note 8 (page 22) of Table 13, " Safety injection,"
has been be revised accordingly. For additional information see the detailed description for Change Request Number IT-96-4.1.
i Change Request Number IT 5. 2 Related SER : 3.9.6 SSER. 26 3.9.6 SER/SSER Impact N
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ENCLOSURE TO TXX-97135 i
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COMANCHE PEAK STEAM ELECTRIC STATION DNITS 1 & 2 INSERVICE TESTING PLAN (IST)
INSTRUCTION SHEET (Page 1 of 1)
_.__T_he_following. instructional.infomation alid checklist is being furnished to help insert Revision 9 into the Comanche Peak Steam Electric Station IST.
Discard the old sheets and insert the new sheets, as listed below.
Remove Insert i
Cover Sheet Cover Sheet Table 9 Page 3 of 12 Page 3 of 12 Table 13 Page 15 Page 15 Page 16 Page 16 i
Page 22 Page 22 Aooendix A Page A 19 Page A-19 List of Effective Paaes EPL 1 through EPL-5 EPL 1 through EPL 5 NOTE: Please complete the entry for insertion of Revision 9 on the " Record of Changes" form located at the beginning of the IST Plan.
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