ML19209A427

Forwards Response to Item 1 of IE Bulletin 79-17, Pipe Cracks in Stagnant Borated Water Sys at PWR Plants. Summarizes Review of Stainless Steel Piping Sys

ML19209A427
Person / Time
Site:	North Anna
Issue date:	09/14/1979
From:	Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-79-17, NUDOCS 7910030844
Download: ML19209A427 (5)

Text

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September 14,lh792 Mr. James P. O'Reilly, Director Serial No. 622C Office of Inspection and Enforcement P0/FHT:baw U. S. Nuclear Regulatory Commission Docket No. 50-338 Region II License No. NPF-4 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Subject:

IE Bulletin 79-17 North Anna Power Station Unit 1

Dear Mr. O'Reilly:

We have reviewed the subject bulletin, " Pipe Cracks in Stagnant Borated Water Systems at PWR Plants", and are forwarding our response to Item 1 for your information for North Anna Power Station Unit 1. If you have any questions or require additional information, please contact this office.

Very truly yours, y

o C. M. Stallings, Vice President-Power Supply and Production Operations Attachment cc: Director, Division of Operating Reactors Office of Inspection and Enforcement Washington, D. C. 20555 1086 172 eB e

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Page 1 Attachment Response to IE Bulletin 79-17 Pipe Cracks In Stagnant Borated Water Systems At PWR Plants North Anna Power Station Unit 1 All safety related stainless steel piping systems were reviewed and the systems or portions of systems which are greater than 215 inches in diameter and contain stagnant oxygenated borated water were identified.

(a) Inservice inspection (ISI) examinations have not yet been performed on the stagnant portions of systems which were identified. The examination required by Item 2 of this bulletin will be completed and the results of the inspections will be reported as requested.

(b) When in service, the water in safety related systems is periodically sampled and analyzed to ensure proper chemistry. The Residual Heat Removal System, for example, is sampled and analyzed prior to placing it in service and during system operation. Safety related tanks, such as the Refueling Water Storage Tank, Boron Injection Tank and Casing Cooling Tank are also sampled and their chemistry maintained as required by the Technical Specifications. At present there is no means to check the chemistry of water which is dead legged because of its inaccessibility for sampling. As a result, the chemistry of the water in these stagnant lines cannot be determined.

(c) Attached is the list of identified systems which have been subjected to preservice inspection. The preservice examinations were performed in accordance with the 1974 edition of ASME Section XI with i Summer 1975 addenda and acceptance criteria determined accordingly.

(d) No cracking has previously been experienced in the stagnant systems which have been identified.

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e 1086 173

Page 2 System Line No. No. of Welds No. of Welds Type of Examination Examined A. Reactor Coolant System

1. Icop 1 Accumulator 12"RC-22 21 21 Liquid Penetrant Discharge 12"SI-67 Visual, Ultrasonic

2. Ioop 1 Hot Leg 6"RC-26 9 9 Liquid Penetrant, Low Head Safety 6"SI-21 Vidusi, Ultrasonic Injection

3. Ioop 1 Cold Ir 6"R M 7 41 41 Liquid Penetrant, Low Head Safety 6"SI-131 Visual, Ultrasonic Injection

4. Ioop 1 8" Bypass 8"RC-11 10 10 Liquid Penetrant Visual, Ultrase,nic

5. Loop 1 3" Drain 3"RC-215 7 7 Liquid Penetrant, Visual

6. Loop 2 Accumulator 12"RC-23 24 24 Liquid Penetrant, Discharge 12"SI-68 Visual, Ultrasonic

7. Loop 2 Hot leg 6"RC-18 8 8 Liquid Penetrant, Low Head Safety 6"SI-19 Visual, Ultrasonic Injection

8. Ioop 2 Cold Leg 6"RC-19 42 42 Liquid Penetrant.

Low Head Safety 6"SI-133 Visual, Ultrasonic Injection

9. Ioop 2 8" Bypass 8" RC-12 10 10 Liquid Penetrant, Visual, Ultrasonic

10. Loop 2 3" Drain 3" RC-217 5 5 Liquid Penetrant, Visual

11. Loop 3 Accumulator 12" RC-24 24 24 Liquid Penetrant, Discharge 12"SI-69 Visual, Ultrasonic 9

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Page 3 System Line No. No. of Welds No. of Welds

'Ibpe of Examination Examined

12. Loop 3 Hot Leg 6"RC-21 9 9 Liquid Penetrant, Low Head Safety 6"RC-16 Visual, Ultrasonic Injection

13. Loop 3 Cold Leg 6"RC-20 57 57 Liquid Penetrant, Low Head Safety 6"SI-132 Visual, Ultrasonic Injection

14. Loop 3 8" Byparn 8" RG-13 10 10 Liquid Penetrant, Visual, Ultrasonic

15. Loop 3 3" Drain 3" RC-219 7 7 Liquid Penetrant, Visual B. Residual Heat Removal

1. Loop 1 Hot Leg to RHR System 14" RH-1 17 17 Liquid Penetrant, Visual, Ultrasonic

2. Varfous RHR System Lines 12"RH-11 15 13 Ultrasonic, Visual

3. 12" RB-15 5 5 Ultrasonic, Visual

4. 12"RH-6 10 6 Ultrasonic, Visual

5. 14"RH-2 21 11 Ultrasonic, Visual

6. 14"RH-3 18 7 Ultrasonic, Visual

7. 10"RH-32 11 6 Ultrasonic, Visual

8. 10"RH-31 3 2 Ultrasonic, Visual

9. 10"RB-8 11 6 Ultrasonic, Visual

10. 10"RB-4 7 4 Ultrasonic, Visual

11. 10"RB-5 5 2 Ultrasonic, Visual

12. 10"RH-7 8 k Ultrasonic, Visual

13. Y 10"RB-9 7 4 Ultrasonic, Visual 1086 175

Page 4 m . .

System Line No. No. of Welds No. of Welds Iype of Examination Examined

14. Various RHR Sytem Lines 10"RH-10 10 5 Ultrasonic, Visual

15. 10"RB-13 2 2 Ultrasonic, Visual

16. 10"RH-14 8 8 Liquid Penetrant, Visual, Ultrasonic

17. 10"RH-12 7 7 Liquid Penetrant, Visual, Ultrasonic 18, 6"RB-19 2 2 Ultrasonic, Visual

19. Y 6"RH-17 2 2 Ultrasonic, Visual C. Safety Injection System

1. Safety Injection 3"SI-139 6 6 Liquid Per etrant, Visual

2. Safety Injection 3"SI-57 17 17 Liquid Penetrant, Visual

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