ML19322A596
| ML19322A596 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/05/1977 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 7911210675 | |
| Download: ML19322A596 (7) | |
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2 Mr. William O. Parker. Jr..
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.We are reviewing your requesti dated October 1.1976, to change the ;
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Occonee Nuclear Station Technical Specifications applicable to y'
Oconee Unit 1. Inservice Inspection Requirements (10 CFR 50.55a).
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We find that we need additional infomation, identified in the..
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enclosure, to continue our review.
It is requested that you provide us with the infomation within; '
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review of your submittal. '
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April 5, 1977
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Docket No. 50-269 Duke Power Company ATTN:
Mr. William 0. Parker, Jr.
Vice President - Steam Production Post Office Box 2178 422 South Church Street Charlotte, North Carolina 28242 Gentlemen:
We are reviewing your request, dated October 1,1976, to change the Occonee Nuclear Station Technical Specifications applicable to Oconee Unit 1 Inservice Inspection Requirements (10 CFR 50.55a).
We find that we need additional information, identified in the enclosure, to continue o r review.
c It is requested that you provide us with the information within 30 days cf receipt of this letter so that we can continue our review of your submittal.
Sincerely, 1HMadL A. Schwencer, Chier Operating Reactors Branch #1 Division of Operating Reactors cc:
See next page
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-s Duke Power Company April 5,1977 cc:
Mr. William L. Porter Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 J. Michael McGarry, III, Esquire DeBevoise & Liberman 700 Shoreham Building 806-15th Street, NW.,
Washington, D.C.
20005 Oconee Public Library 201 South Spring Street Walhalla, South Carolina 29691 e
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ENGINEERING BRANCH
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Request for Additional Information Inservice Inspection Requirements
' Comments
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1.
Provide additional information using the letter from A. Schwencer, Chief, OR3 #1 to W. O. Parker, Jr., Vice-President, Steam Production Duke Power Co., dated November 30, 1976, as guidance, to justify the request for relief from the inservice examination requirements speci-fied in the 1974 edition of the Section XI Code through the summer 1975 addenda for Code Class.1, 2 and 3 components.
2.
Clarify whether the required inservice examination will be witnessed or verified by a third party inspector even though South Carolina is not an ASME Code state.
. Comments 1.
In order to evaluate the Oconee 1 pump testing program the following information is requested:
j a) A list identifying each pump to be tested by system and application.
.r b)
The test parameters that will be measured for each pump.
c) The test intervals, i.e., monthly during operation or only during cold shutdown.
2.
When certain parameters are not going to be tested and relief is re-quested, provide the folicwing information:
a)
Specifically identify the ASME Code ' requirement that has been determined to be impractical for the pump.
b)
Provide information to support the determination that the require-l ment in (a) is impractical.
t c)
Specify the inservice testing that will be performed in lieu of the ASME Code Section XI requirements that have been determined to be impractical or provide the basis for operation of this pump without this ISI.
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Provide the schedule for implementation of *he procedure (s) in (c) above.
- Comments
'f 1.
Provide code class. designations for all valves tested.
2.
On your table identify each valve in AEKE Section XI Cat. A that will be leak tested during refueling. outages.
3.
Provide the test intervals for all valves to be tested.
For check i
valves, identify those that will be exercised only during cold shutdown.
1 4.
Where relief has been requested from certain requirements of the code, specify the inservice testing that will be performed in lieu of the ASME Code Section XI requirements that are impractical or provide the bases for operation of this valve without this ISI.
Also provide the schedule for implementation.of this testing.
5.
Provide simplified pipin; diagrams of systems which cust function to safely shutdown the plant or mitigate the consequences of an accidene.
Active components on the above systems which must change position should be identified. A1so, provide a narrative description of the valve line-ups required of the systems identified above each of their safety functions.
6.
In addition to the above comments we have found that in some cases, valves important to plant safety were omitted.
Co=ments on these valves will be made by drawing number.
.a)
Dkg PO-100-A-1 Only 2 of the three pressurizer re'1ief valves are
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listed.
Valve # 1RC-66 should be included.
b)
Dwg PO-101A Valves listed on this drawing are containment iso-lation valves.
Check valve #HP-194 should be included if possible to. the test program.
c) Dwg PO-102A Valves BS-3 and BS-4, Power operated valves on the suction lines to the reactor building spray pumps are omitted.
They should be included or justification provided for not including them.
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Check valves BS-14 and BS-19 are proposed
.d)
Dwg PO-103A-1,2,3 to be tested every 5 years.
A source of instrument air exists (according to the drawing) for spray nozzle testing.
The licensee should consider using the instrument air ~to test the check valves on a more frequent schedule.
e)
Dwg PO-122A Only one of sixteen main steam safety reliefs is listed. Provide justification for not including the others.
f)
Dvg PO-127-B - We cannot locate N2 isolation valves 1N-91 thru 1N-94.
These may be mis-numbered on submittal.
They abould be N-105, 106, and 107.
Confirm and correct technical specification as required.
I - Comments 1.
Because of difference in the date of start of facility commercial opera-tion for Oconee Units 1, 2 and 3, we recommend that separate Technical Specifications be established for each unit.
2.
The language in the Technical Specifications 4.04 and 4.2.1 is not acceptable. The sample technical specification language recommended in the letter from R. A.. Purple, Chief, Operating Reactors Branch #1, NRC to Duke Power Company, dated April 26, 1976 should be used, i.e.
4.2.1 - Inservice inspection of ASME Code Class 1, 2 and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief,has been granted
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by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
4.0.4 Inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section. 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).
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3.
Technical Specifications 4.2.6 regarding the pump flywheel inservice inspection program is not acceptable.
We require that a surface examination of all exposed surfaces and a complete volumetric exami-nation, during the plant shutdown coinciding with the inservice in-spection schedule as required by the Section XI Code be performed at approximately ten-year intervals, in addition to the in-place volu-metric examination of the bore and keyway of each reactor coolant pump flywheel at approximately three-year intervals as specified in Technical Specifications 4.2.6.
Removal of the flywheel is not required.
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