ML20073L640

Forwards Rev 4 to CPSES Unit 1 & 2 IST Plan for Pumps & Valves First Interval

ML20073L640
Person / Time
Site:	Comanche Peak
Issue date:	10/07/1994
From:	Terry C TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20073L647	List: ML20073L640 ML20073L659
References
TXX-94261, NUDOCS 9410130230
Download: ML20073L640 (6)

Text

,.

- Log # TXX-94261 llllllllll7 = File # 10010

""""' 7 905.4

___. .-'- Ref. # 10CFR50.55a(f)

7UELECTRIC october 7, 1994 C. lance Terry Grump Yke President U. S. Nuclear Regulatory Commission Attention: Document Controi Desk 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 4 (1989 EDITION OF ASME CODE, SECTION IX, NO ADDENDA; UNIT 1 INTERVAL START DATE: AUGUST 13, 1990, FIRST INTERVAL; UNIT 2 INTERVAL STAPsT DATE: AUGUST 3, 1993, FIRST INTERVAL)

Gentlemen:

Enclosed is Revision 4 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 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 effective date of this revision is October 13, 1994, at 12:01 AM CST.

The attachment provides a detailed description of the changes made by Revision 4 to the Plan in a format identical to that provided for changes to the Final Safety Analysis Report (FSAR). All changes daccribed in the 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 TV 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."

94101:30230 941007 ,O DR ADOCV 0500 5 4ao N. otive LB. si Dattas, Texas 75201 w

TXX-94261 Page 2 of2 If you have any questions, please call Mr. Carl Corbin at (214) 812-8859.

Sincerely, C. Lance Terry By:

D. R. Woodlan Docket Licensing Manager CBC/grp Attachment Enclosure c- Mr. L. J. Callan, Region IV Resident Inspectors, CPSES (2)

Mr. T. A. Bergman, NRR Mr. G. Bynog, TOLR (clo)

Mr. J. C. Hair, Authorized Nuclear Inservice Inspector

Attachment'to TXX-94261 October 7, 1994 Page 1 of 2 CPSES - INSERVICE TEST PROGRAM ( IST )

AMENDMENT / REVISION 4 DETAILED DESCRIPTION IT Page (as amended) Group Description Table 13- 2 See Sheet No (s) :5, 14, 15 and Notes Section Pgs 3, 4 Revises test frequency for Low Head Safety-Injection check valves 8818A, 8818B, 8818C, 8818D, 8948A, 8948B, 8948C, and 8948D from cold shutdown to refueling outage.

Revises Note 7 to remove reference to valves listed above.

kddsNote9toclarifythetestingfrequencyforthe valves listed above.

Revision  :

Currently, each valve listed above is open full-stroke tested by acoustic emission testing at Cold Shutdown. This revision changes the requirement to an open partial-stroke test every Cold Shutdown and an open full-stroke test every Refueling Outage.

Also at each Refueling Outage, in lieu of flow testing all eight valves and listening to each with acoustic emission monitoring equipment, all eight valves will be flow tested and only two valves tested using acoustic emission monitoring.

To obtain a proper acoustic signature, both RHR Pumps are required to flow through the check valve being tested. Also, all Reactor Coolant Pumps need to be secured to lower background noise sufficiently to record the acoustic signature. Since the test requires the flow of both trains of Residual Heat Removal to be secured and all Reactor coolant Pumps to be secured, Cold Shutdown testing is not practicable. ,

The acoustic emission monitoring of the valves will be performed on one valve per group per outage on a I rotating schedule each time testing is performed (a sampling program). The groups will be four valves each, 8818A, B, C, D and 8948A, B, C, D. If problems are found with the sample valve, all valves in the affected group must be tested using acoustic emission monitoring during the same outage.

This nonintrusive technique meets the Code requirements for verifying disk movement for the full-stroke exercising - opening - of check valves.

The nonintrusive reverification allows flow testing at repeatable conditions to be performed on all valves in a group while requiring

Attachment to TXX-94261 Octob'er 7, 1994 Page 2 of 2 IT Page (as amended) Group Description nonintrusive tests of only one of the group on a rotating schedule. Relief is not required because this test method is considered an acceptable "other positive means."

Change Request Number  : IT-94-4.1 Commitment Register Number :

Related SER

• 3.9.6 SSER :26 3.9.6 SER/SSER Impact  : No Table 14- 3 See Sheet No (s) :1 and Notes Section Page 1 Adds note 3 to clarify testing requirements for check valves 2SW-0016, 23W- 0017, 2SW-0084, and 2SW-0085 due to the scheduled removal of the valve internals during the first refueling outage for Unit 2.

Update  :

The internals of the Unit 2 check valves are scheduled for removal during the first refueling outage for Unit 2. After Minor Modifications93-567 and 93-568 have been accepted by operations, testing is no longer required. The test requirements remain valid until the internal (s) are removed. These valves are not required to perform a " closed" safety j function. j Change Request Number  : IT-94-1.1  :

Commitment Register Number : j Related SER : 3.9.6 SSER :26 3.9.6 .

SER/SSER Impact  : No l Table 14- 3 See Sheet No (s) : Notes Section Page 1 ,

Revises note 1 to clarify testing requirements for I check valves 2SW-0388 and 2SW-0389 due to the )

scheduled removal of the valve internals during the first refueling outage for Unit 2.

Revision  :

The internals of the Unit 2 check valves are scheduled for removal during the Unit 2 Refueling Outage No. 1. After Minor Modification 93-497 has been accepted by operations, testing is no longer required. The test requirements remain valid until the internal (s) are removed. These valves are not required to perform a " closed" safety function.

Change Request Number  : IT-94-5.1 Commitment Register Number : 1 Related SER : 3.9.6 SSER :26 3.9.6 l SER/SSER Impact  : No i

I

J COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES FIRST INTERVAL INSTRUCTION SHEET (Page 1 of 1)

The following instructional information and checklist is being furnished to help insert Revision 4 into the Comanche Peak Steam Electric Station IST.

Discard the cid sheets and insert the new sheets, as listed below.

Remove Insert Record of Changes Cover Sheet Cover Sheet Table 13 Page 5 of 17 Page 5 of 17 Page 14 of 17 Page 14 of 17 Page 15 of 17 Page 15 of 17 Notes, Page 3 Notes, Page 3 Notes, Page 4 Table 14 Page 1 of 3 Page 1 of 3 Notes, Page 1 Notes, Page 1 Effective Pace Listing EPL-1 thru EPL-5 EPL-1 thru EPL-5

, NOTE: Please complete the entry for insertion of Revition 4 on the " Record of Changes" form located at the beginning of the IST Plan.

l

COMANCIIE PEAK STEAM ELECTRIC STATION

.. INSERVICE TESTING PLAN RECORD OF CIIANGES

.!ST Revision Date of Date Date Entered by No. Revision Received Entered (Print / Type anc; Signature)

I through 3 * * *

• 4 l

1 Revisions I through 3 have been previously is;ued. See effective page list for dates of Revisions.

NOTE:The date of the last effective Revision can be confirmed by contacting Docket Licensing at (214) 812 4340. The List of Effective Pages identifies all Revisions.

ROC-1 Ocotober 7,1994 l

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