ML16152A352
| ML16152A352 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/17/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8408270464 | |
| Download: ML16152A352 (10) | |
Text
,
August 17, 1984 Dockets No. 50-269 Distribution:
50-270 Docket File and 50-287 Reading File Gray File ACRS 10.
Charotte Noth Crolna 2242NRC
& L PDR Mr. Hal B. Tucker DEisenhut Vice President - Steam Production ED Duke Power Company P. 0. Box 33189 JNGrace 422 South Church Street EBlackwood Hrnstein
Dear Mr. Tucker:
We have reviewed the pump and valve inservice testing (1ST) for the remainder of the current (Unit 1) and upcoming (Units 2 and 3) 120 month testing intervals (Unit 1):
7/15/83-7/15/93; Unit 2:
9/9/84-9/9/94; Unit 3:
12/16/84-12/16/94).
Enclosed is a list of questions generated during our preliminary review. We request that a conference call be arranged with your staff who are able to provide the appropriate technical expertise.
Your Oconee project manager, Ms. Helen Nicolaras will call your staff to make final arrangements for the conference call.
Sincerely, Ii)
John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing
Enclosure:
As stated cc w/enclosure:
See next page ORB' *7 DL OR B~to De aras;ef JFS r 8/f4 /84 86/4 340327046 4 840817 PR ADOCK 050026, PW put
Duke Power Company cc w/enclosure(s):
Mr. William L. Porter Duke Power Company P. 0. Box 33189 422 South Church Street Office of Intergovernmental Relations Charlotte, North Carolina 28242 116 West Jones Street Raleigh, North Carolina 27603 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission, Region II 101 Marietta Street, Njq, Suite'2900 Atlanta, Georgia 30323 Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Reqional Radiation Representative Columbia, South Carolina 29201 EPA Region IV 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Mr. J. C. Bryant Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 J. Michael McGarry, III, Esq.
Bishop, Liberman, Cook, Purcell & Reynolds 1200 17th Street, N.W.
Washington, D. C. 20036
ENCLOSURE A. General Questions and Comments
- 1. For testing of valves during cold shutdowns, it is the NRC position that the licensee is to commence testing as soon as the cold shutdown condition is achieved but not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown, and continue until complete or the plant is ready to return to power. For planned cold shut downs, where ample time is available for testing all the valves identified for the cold shutdown frequency in the IST program, exceptions to the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> may be taken. (Refer to Item 3.1)
- 2. Provide the limiting value of full-stroke time for each Category A or B power-operated valve in the IST program.
- 3. Are Category A valves that perform a pressure isolation function only and Category A valves that perform a containment isolation function only tested to the same acceptance criteria?
(Item 3.5.a)
- 4. Clarify Item 3.5.b., i.e., is corrective action initiated when valve actual full-stroke time exceeds the specified full-stroke time? Is relief being requested from IWV-3417(b) for all power-operated valves in the IST program?
- 5. Passive valves should be identified in the I T program.
1
- 1. Provide the specific technical justification for not exercising valves 1RC-155, -156, -157, -158, -159, and -160 quarterly.
- 2. Review the safety function of valves 1RC-162 and 1RC-163 to determine if they should be categorized A.
C. High Pressure Injection System
- 1. Why were valves 1HP-26, -27, and -120 changed from Category A to Category B?
- 3. Do valves 1HP-144, -145, -146, and -147 have to change position to perform a safety function?
- 5. Do valves 1HP-283, -284, -286, -393, and -394 have to change position to perform a safety function?
D. Low Pressure Injection
- 1. Why were valves lLP-l and lLP-2 changed from Category A to Category B?
Do these valves perform a pressure isolation function?
E. Low Pressure Service Water
- 1. Why were valves lLPSW-6 and lLPSW-15 changed from Category A to Category B?
F. Main Steam
- 1. Should valves 1MS-102, -103, -104, and -105 be Category B?
2
G. Reactor Building Purge
- 1. Why is the exercising frequency of valves 1PR-3 and 1PR-4 different than valves 1PR-1, -2, -5, and -6?
- 2. What are the requirements of Technical specification 3.8.7?
H. Reactor Building Spray
- 1. Provide the specific technical justification for not full-stroke exercising valves 1BS-7 and 1BS-9 quarterly.
I. Demineralized Water
3
The following valves are exercised during cold shutdowns or refueling outages but no justification has been provided.
1HP-409 1HP-410 lLP-17 lLP-18 1LP-46 lLPSW-7 lLPSW-8 lLPSW-9 lLPSW-10 lLPSW-11 lLPSW-12 lLPSW-13 lLPSW-14 1RC-155 IRC-156 1RC-157 1RC-158 1RC-159 1RC-160 4
The following valves are never full-stroke exercised and relief from exercising has not been requested.
1BS-7 lBS-9 1HP-144 1HP-145 1HP-146 1HP-147 1HP-283 1HP-284 1HP-286 1HP-393 1HP-394 5
The following valves are exercised during cold shutdowns or refueling outages but no justification has been provided because that test frequency has been previously approved by the NRC.
1CC-7 1HP-120 1CC-8 1HP-126 1FDW-33 1HP-127 1FDW-35 1HP-152 1FDW-36 1HP-153 1FDW-38 1HP-188 1FDW-39 1HP-194:
1FDW-42 lLP-1 1FDW-44 lLP-2 1FDW-45 lLP-31 1FDW-47 1LP-33 1FDW-48 lLP-47 1FDW-232 lLP-48 1FDW-233 lLP-103 1HP-5 lLP-104 1HP-20 1LP-105 1HP-21 lLPSW-6 1HP-26 lLPSU-15 1HP-101 lMS-102 1HP-102 lMS-103 1HP-105 lMS-104 1HP-109 lMS-105 1HP-113 6
The following valves are never full-stroke exercised and relief from exercising has not been requested because these valves have been previously reviewed and approved by the NRC.
1BS-5 1BS-6 lBS-11 lBS-14 lBS-16 lBS-19 1CC-20 1CC-24 1CC-76 1CC-77 1CF-11 1CF-12 1CF-13 1CF-14 1CS-11 1CS-12 1DW-155 1DW-156 1LP-29 1LP-30
Missing P&IDs 115U 0-472 115R 115S