ML20076E095
| ML20076E095 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/12/1983 |
| From: | Beckham J GEORGIA POWER CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20076E099 | List: |
| References | |
| TAC-11260, TAC-11261, TAC-55236, NUDOCS 8308240127 | |
| Download: ML20076E095 (5) | |
Text
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Georgia Pcwer Company 333 Piedmont Avenue Atlanta. Georgia 30308 Telephone 404 526J020 Maung Address Post Offce Bcx 4545 Atlanta. Georg.a 30302 b
Georgia Power J. T. Beckham, Jr.
- ne scuthern electnc system Vce President and General Manager Nuclear Generatico August 12, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 tRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1,=-2 INSERVICE INSPECTION PROGRAM Gentlemen:
Georgia Power Company (GPC) hereby submits for your review a ' revision of the inservice inspection programs for Hatch Units 1 and 2.
The enclosed revision voluntarily updates the programs to the 1980 Edition of the ASME Section XI Code with Addenda through Winter 1980.
This inservice inspection program update supercedes the earlier Hatch Unit 1 program with relief requests submitted by letter dated January 27, 1981, and the Hatch Unit 2 program which was originally submitted in the Final Safety Analysis Report.
The aforementioned superceded programs for Hatch Units 1 and 2 were written to the 1974 Edition of the ASME Section XI Code with Addenda through Summer 1975.
Six (6) copies of the ' updated program have been enclosed for your convenience.
The upgraded programs will go into effect on January 1,1984, and will be implemented for a period of 80-months.
Near the end of the 80-month period, the inservice inspection programs will again be updated to meet a later,
NRC-approved edition of ASME Section XI.
The 80-month duration of Re -
upgraded programs is being used so that the start date of the following 120-month interval of the inservice inspection programs for the two Hatch units will coincide.
Revision of the pump and valve inservice testing portions of the inservice inspection programs involved two major tasks:
1)
Incorporating changes as required by the 1980 Edition of ASME Section XI with Addenda through Winter 1980; and, 2)
Incorporating changes -and responding to questions as a result or the review of the pump and valve inservice testing portions of the previous programs by NRC Region II as requested by NRC NRR.
/ 047 8308240127 830812
/
gDRADOCK 05000321
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k Georgia Power n Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 August 12, 1983 Fage Two A meeting was held on June 23, 1983 among NRC Region II, NRC NRR, and GPC personnel to discuss NRC questions concerning the previous pump and valve inservice testing portions of the inservice inspection programs.
The revised pump and valve inservice testing programs in the document enclosed herein incorporates GPC's responses to the informally submitted NRC questions.
Enclosed as Attachment A to this letter is a list of changes from the previous pump and valve inservice testing portions of the inservice inspection programs to the upgraded programs.
It should be noted that for two systems mentioned by the NRC during the June 23, 1983 meeting, GPC has not included them in the pump and valve inservice testing portions of the inservice inspection programs.
The two
' systems are the Diesel Generator Fuel Oil System and the Diesel Generator Starting Air System.
It is the position of GPC that these two systems are not within the scope of Section X1 as defined in NRC Regulatory Guide 1.26 and that the requirements of the Technical Specifications adequately test these systems to ensure the operational readiness of the diesel generators.
The operability of the diesel fuel transfer pumps are verified monthly per Technical Specification requirements.
The operability of the starting air system is verifiec monthly during the diesel generator test required by Technical Specifications.
GPC requests that NRC grant the relief requests included in the attached programs document in accordance with 10CFR50.55a (g) (6).
Relief requested in the upgraded inservice inspection programs does not affect public health and safety.
Please be' advised that the inservice inspection plans which implement the enclosed programs document for Hatch Units 1 and 2 will be revised prior to January 1,1984, and will be available for review by NRC at the Hatch plant site.
Since portions of the upgraded inservice inspection programs respond to NRC questions, GPC requests that the enclosed programs document be reviewed by the NRC by January 1,1984.
GPC will implement the updated programs for the two Hatch unit.s on that date.
703 3
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_ _ _. _ _ _~.. _ -- _ _ _. _ _. _ _ _ _ _ _ _. _.
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Georgialbwer d l
Director of Nuclear Reactor Regulatfon Attention: Mr. Jehl F. Stolz, Chief 1
Operating Reactors Branch No. 4 i-August 12, 1983 i
Page Three l
By copy of this letter, NRC Region II is being provided with the enclosed i
information.
Should you have any questions or comments in this regard, please contact j
this office.
Sincerely yours, bg I
J. T. Beckham, Jr.
JAE/bim i
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Enclosures:
Attachment A
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i Hatch 1 and 2 ISI Frogram yc: L. T. Gucwa H.
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Nix, Jr.
Senior. Resident Inspector J. P. O'Reilly (W C Region II)
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ATTACHENT A The following is a listing of significant changes from the pump and valve inservice testing portion of the inservice inspection programs (1974 Code) to J
1 the program upgraded to the requirements of the 1980 Edition of ASME Section XI with Addenda through Winter 1980:
l General 1.
There are no significant changes to the pump program except that the relief request for quarterly testing has been deleted.
I 2.
The Control Rod Drive System valves were placed in the valve program; however, they will be tested per the requirements of the Technical Specifications.
3.
Category A valves that are " Appendix J" valves will have a specific leakage applied.
4.
Category A valves that are " pressure isolation" valves will have a leakage i
criteria of.5 gpm per inch of valve diameter or a maximum of 5 gpm total
- leakage, r
Speelfic Valves l
1.
Valves P41-F311 A through 0 were added to the program.
i 2.
Valves E41-F012 and 2E41-F012 will now be stroke timed.
3.
Valves E41-F008 and2E41-F008 are reclassified as passive valves.
4.
Flow control valves E41-F035 and 2E41-F035 will be observed during pump testing to ensure that they fail in the "open" position.
5.
The following check valves will be disassembled and inspected as scheduled in the program to prove they are functional:
l Ell-F050 A & B E41-F049 P41-F024 A & B E21-F006 A & B E51-F001 P41-F025 A & B E41-F021 E51-F002 P41-F026 A & B E41-F022 E51-F028 P41-F028 A & B E41-F040 E51-F040 E41-F045 2 Ell-F050 A & B 2E41-F049 2P41-F024 A & B 2E21-F006 A & B 2E51-F001 2P41-F025 A & B 2E41-F021 2E51-F002 2P41-F026 A & B 2E41-F022 2E51-F028 2P41-F028 A & B 2E41-F040 2E51-F040 2E41-F045 4
.-.. - ~. - - -... - -.
i ATTACHMENT A (CONTINUED) 6.
The following air-operated valves will be stroke timed; however, a maximum stroke time is the only acceptance criteria:
P41-F035 A & B 2P41-F035 A & B P41-F036 A & B 2P41-F036 A & B P41-F037 A & B 2P41-F037 A & B P41-F039 A & B 2P41-F039 A & B P41-F040 A & O 2P41-F040 A & B P41-F042 A & B 2P41-F042 A & B August 12, 1983
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