ML20010C103
| ML20010C103 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/07/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8108190122 | |
| Download: ML20010C103 (6) | |
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LB#1 Rdg TERA AUG 7 1981 BJYoungblood NRC/PDR DEisenhut L/PDR MRushbrook NSIC Docket No.: STN 50-482 GEdisor.
TIC RVollmer ACRS~(16)
TMurley Mr. Glenn L. Koester RMattson Vice President - Nuclear RHartfield, MPA Kansas Gas and Electric Company WJohnston 201 North Market Street WHouston Post Office Box 208 AChu l
Wichita, Kansas 67201 KDempsey
Dear Mr. Koester:
1
Subject:
Wolf Creek FSAR Site Addendum - Request for Additional Information -
Initial Test Program As a r ssult of our review of your application for operating licenses we find that we need additional information regarding the Wolf Creek FSAR site addendum.
The specific information required is as a result of our review of the initial test program and is listed in the Enclosure.
To maintain our licensing review schedule for the FSAR, we will need responses totthe enclosed request by October 1, 1981.
If you cannot meet this date, please inform us within seven days after receipt of this letter of the date you plan to submit your responses so that we may review our schedule for any necessary changes.
Please contact Dr. G. E. Edison, Wolf Creek Licensing Project Manager, if you desire any discussion or clarification of the enclosed request.
Sincerely,
/
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Robert L. Tedesco, Assistant Director
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for Licensing Division of Licensin C
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Enclosure:
As stated h gG ).T esw s cc: See next page 1
o. -sa, p 8108190122 810807 N
PDR ADOCK 05000482
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Mr. Glenn L. Kocster Vice President - Nuclear Kansas Gas and Electric Company 201 North Market Street P. O. Box 208 Wichita, Kansas 67201 cc: Mr. Nicholas A. Petrick Ms. Wanda Christy Executive Director, SNUPPS 515 N. 1st Street 5 Choke Cherry Road Burlington, Kansas 66839 Rockville, Maryland 20750 Eric A. Eisen, Esq.
Mr. Jay Silberg, Esquire Birch, Horton, Bittner & Monroe Shaw, Pittman, Potts & Trowbridge 1140 Connecticut Avenue, N. W.
1800 M Street, N. W.
Washington, D. C.
20036 Washington, D. C.
20036 Kansans for Sensible Energy Mr. Donald T. McPhee P. O. Box 3192 Vice President - Production Wichita, Kansas 67201 Kansas City Power and Light Company 1330 Baltimore Avenue P. O. Box 679 Kansas City, Missouri 64141 Ms. Mary Ellen Salva Route 1, Box 56 i
Burlington, Kansas 66839 Ms. Treva Hearne, Assistant General Counsel Public Service Commission P. O. Box 360 Jefferson City, Missouri 65102 Mr. Tom Vandel Resident Inspector / Wolf Creek NPS
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c/o U.S.N.R.C.
P. O. Box 1407 Emporia, Kansas 66801 Mr. Michael C. Kenner Wolf Creek Project Director State Corporation Commission State of Kansas Fourth Floor, State Office Bldg.
Topeka, Kansas 66612 f*
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SNUPPS-WC page 1 of 4 ENCLOSURE WOLF CREEK - QUESTION 640.0WC Procedures and Test Review Branch
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640.lWC Subsection 14.2.2.4.4 states that GE will be responsible (14.2.2.4) for providing personnel experienced in the startup and operation of the turbine generator and related auxiliary equipment.
Expand Subsection 14.2.2.4.4 to explain in greater detail what direct support GE will provide (ex.,
]
supply and install turbine ' generator, instruct KG&E personnel in the conduct of testing and operation, recommend procedures for starting, operating, and shutting down equipinent).
640.2WC Subsection 14.2.2.6 refers to Section 13 regarding the (14.2.2.6) qualifications of key personnel involved in the initial testing program.
Subsection 13.1.3.1 references Regulatory Guide 1.8.
Our current position is that the individuals involved in' preoperational or startup testing should hold the qualifications stated in Regulatory Position 3 of proposed Revision 2 to Regulatory Guide 1.8, February 1979 (issped for comment).
State that your minimum qualification requirements will be in accordance with this regulatory position or provide justification for recuiring any lesser qualifications.
640.3WC Section 14.2.5 states that during Power Ascension Testing, (14.2.5) review and approval of initial startup test procedure results is completed for each of the plateaus.
The first plateau is at 30%.
In Section 14.2.11 of SNUPPS, a 25%
power level is referenced.
This is given as the power level which will not be exceeded until major plant test requirements are completed satisfactorily.
Modify Section 14.2.5 to clarify how the applicable startup test results will be reviewed prior to exceeding 25% power as referenced in Section 14.2.11 of SNUPPS.
640.4WC Appendix 3A states in the Section on Regulatory Guide l'.58 (14.2.7) that an alternative method for qualifying nuclear power plant inspection, examination and testing personne'l will
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SNUPPS-WC page 2 of 4 9
2 be used.
Insufficient detail is available to determine-i whether or not the alternative qualification program provides l
the ;ame quality training.
Expand the description of the alternative qualification method in Appendix 3A or delete this exception to Regulatory Guide 1.58.
Note: Regulatory i
Positions C.5, 6, 7, 8, and 10 of Regulatory Guide 1.58 (Rev.1, 9/80) apply to the Wclf Creek nuclear station.
640.5 WC Subsection 14.2.8.2 of SNUPPS refers to Section 14.2.8 of (14.2.8.2) the Site Addendum for additional site specific information.
SNUPPS-WC contains no such inforr:ation.
Provide the following:
(1) Specify which individual at Wolf Creek will be responsible for incorporating reactor ope.ating and testing experiences of similar power plants during the Initial Test Prog am.
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(2) Subsection 14.2.8.1 af SNUPPS only references development of preoperational test procedures.
Provide information i
on how information or other plant's experiences will be
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'ised in the' preparation of Phase II-IV testing.
640.6 WC Certain terminolt gy used in the individual test descriptions j
(14.2.12) does not clearly indicate the source of the acceptance j
criteria to be used in determining test adequacy. An l
acceptable format for p;oviding acceptance criteria for test results includes any of the following:
Referencing technical specifications l
Referencing specific sections of the FSAR Referencing vendor *.achnical manuals i
Providing specific quantitative bounds (only if the information cannot be provided in any of the above ways).
Modify the individual test description subsection presented below or, if applicable, add a paragraph to Subsection 14.2.12 3
i that provides an acceptable description of each of the unclear terms.
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i (1) Within design specification 14.2.12.1.1 1.2 j-1.3 2.1 2.2 2.3 1
(2)
In accordance with design 14.2.12.1.1 j
(3)
Responds properly I
14.2.12.1.2 2.1 2.2 2.3 640.7WC Verify that the ultimate heat sink cooling pond j
(14.2.12)
(Subsection 9.2.5) is tested to demonstrate adequate j
NPSH and the absence of vortexing over range of basin level from maximum to the minimum calculated 30 days fqllowing LOCA.
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640.8 WC Table 14.2-1 (Sheet 4) of SNUPPS states that for S-X3GD01,
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(14.2)
S-X3EF01, and S-X3NG01 tSe X in the test numbers will be a U or a K, depending on the test site.
In SNUPPS-WC, l
Section 14.2.12, the tests are listed as S-13GD01, S-3E701, and S-3NG01. Modify Section 14.2.12 of SNUPPS-WC or Table 14.2-1 of SNUPPS to eliminate this discrepancy (the test numbers on the non-safety related test.= should also be corrected).
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4 SNUPPS-WC page 4 of 4 Errata--SNUPPS-WC Page Section 14.2 - 1 14.2.2.2 Figure 14.2.1" should be Figure 14.2-1" 14.2 - 8 14.2.3.2.2 assure" should be " ensure" 14.2 - 11 14.2.12.1.1.1 0bjectves" should be " Objectives"
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