ML18219C190

Response to IE Circular No. 76-05 & Provide Information on Action to Be Taken by Licensee.

ML18219C190
Person / Time
Site:	Cook
Issue date:	03/10/1977
From:	Dolan J American Electric Power Service Corp
To:	James Keppler NRC/RGN-III
References
IEC-76-005
Download: ML18219C190 (6)

Text

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AMERICAN ELECTRIC PGV/ER Servi ce Cor porati n~

on 2 Broadtcay, Ncw York, N. Y. E0004 E2) 422.4800 ZOElh F DOE.QE Sonior ZnoutiooViooPrtoidtnt Engintonng 4 Consttuction March 10, 1977 Donald C. Cook Huclear Plant Unit Hos. 1 Sc 2 Docket: Ho. 50-315 and Ho. 50-316 DPR. No. 58 and CPPR Ho. 61 Mr. J. G. Keppler, Regional.'Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region XXX

'99 Roosevelt Road Glen Ellyn, Xllinois 60137 Dear Mr. Keppler-This letter is in response to your letter of October 8, 1976, which was received October 10, 1976 and which transmitted XE Circular Ho. 76-05. On January 10, 1977 we provided the required responses for Unit No. 1 and requested a 60 day extension to respond to items 1,2, and 3 of'he Circular for Unit No. 2 due to a delay in obtaining all the necessary information for Unit Ho. 2 snubbers from XTT Grinnell.

The numbered paragraphs below are in response t;o items 1,2, and 3 for Unit, Ho. 2 in the "Action to be taken by Licensee" section of your letter.

safety related systems in Unit. Ho. 2 having cont:rol valve serial numbers in the B-0001 through B-2000 range:

Mr. J. G. Keppler ~,. March 10, 1977

\

'control Valve Snubber Mark No. Serial Number Pi in S stem

1. 2-GRC-S-626 B-0770-Sl-D71C Reactor Coolant System 2~ 2-GRC-S-609 B-0462-S1-D71C, Reactor Coolant System

3. 2-GRC-S-598 B-1535-Sl-D71C Reactor Coolant System 4 ~ 2-GRC-S-632 B-15 19-S 1-D7 1C Reactor Coolant System

5. 2-GRC-S-632 B-0459-S 1-D7 1C Reactor Coolant System

6. 2-GRC-S-538 B-0100-Sl-D71C Reactor Coolant System

7. 2-GRC-S-592 B-1441-A2 Reactor Coolant System

8. '2-GRC-S-594 B-0607-A2 Reactor Coolant System

9. 2-GRC-S-629 B-0604-Z2 Reactor Coolant System

10. 2-GRC-S-596 B-0619-Al Reactor Coolant System

11. 2-GRC-S-599 B-1515-Sl-D71C Reactor Coolant System

12. 2-GCS-S-729 B-0686-S 1-D71C Chemical Control System

13. 2-GCCW-S-550 B-0463-Sl-D71C Component Cooling Water

14. 2-GCCW-S-519 B-0103-S 1-D71C Component Cooling Water

15. 2-GCCW-S-52 1 B-0097-SP Component Cooling Water Xtem 1. b)

The test. results obtained at XTT Grinell's Warren, Ohio plant are given below for each of the ab'ove 1'isted snubbers. There has been no maintenance of any kind per-formed. on these snubbers since they were calibrated and tested by XTT Grinnell prior to installation on Unit 2 systems.

Lockin Velocit Bleed Velocit Snubber No. Tension Tension Com ression (in/min.) (in. /min. ) (in./min.) (in./min.)

l. 7.9 8.0 4.3 4.0 2 ~ 7.9 8.0 4~4 4.3

3. 8.3 7.4 4.0 4.0 4 ~ 8. 2. 7.6 4.1 4.0

5. 7.9 8.4 4.0 4.2

6. 7.3 8.2 '4.0 3.8

7. 8.4 8.1 3.9 4.1

8. 8.2 8.3 3.9 4.1

9. 8.2 8.2 4.2 4.0

10. 8.3 8.0 4.0 4.1

11. 7.6 7.5 3.8 3.8

12. 8.2 7.6 4.0 4.0

13. 8.0 7.9 4.2 4.1

14. 7.8 8.1 4.1 3.9

15. 8.3 7.9 4.0 4.3

~ ~..~~Mr. J.~ G.~ Kepplex - 3 -' rch 10, 1977 Xtems 1. ~ c and d k

The response to this question for Unit 2 snubbers is identical to the responses given in our letter of January 10, 1977 which addressed the Unit 1 snubbers with the -following exception.

XTT Grinnell has recently infoxmed us 'that it has requalified the 5" x 5" snubber to meet the following bleed rate .undex the specified load conditions: 3.0 in./min +1.0 in./min. The AEPSC Specification document DCC PM 402 QCN, Revision 2, shall be updated to reflect this change in qualification and all future testing and any recalibration of the bleed rate for this size snubber shall meet the above specified criterion. Hence, all size snubbers will not be pe mitted to have a bleed rate of less than 2.0 in./min. undex rated load fox both Unit No. 1 and Unit No. 2.

Xtem 2.

Documentation defining the lock-up and bleed velocities fox the Unit 2 snubbers will be available in the Donald C. Cook Nuclear Plant Quality Assurance "Master Pile."

Item 3.

Maintenance and modification procedures for Unit 2 snubbers will be the same as those for Unit 1 snubbers as described in our letter of January 10, 1977.

Very truly yours, John E. Dolan Senior Executive Vice President Engineering and Construction JED:mam cc: Dr. E. Volganau, 'irector X&E, U.S.N.R.C.

G. Charnoff R. C. Callen P. W. Steketee R. Walsh R. J. Vollen R. W. Jurgensen Bridgman.

R. S. Hunter

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