IR 05000482/1997201
| ML20205E080 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/30/1999 |
| From: | Mel Gray NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| 50-482-97-201, TAC-M98738, NUDOCS 9904050044 | |
| Download: ML20205E080 (25) | |
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UNITED STATES *
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. - *1
\*****/ MaNh 30,1999 LICENSEE: Wolf Creek Nuclear Operating Corporation FACILITY: Wolf Creek Generating Station, Unit 1 SUBJECT: MEETING WITH WOLF CREEK NUCLEAR OPERATING CORPORATION (WCNOC) REGARDING PROPOSED CHANGES TO BATTERY TECHNICAL SPECIFICATIONS SUBMITTED AS PART OF WCNOC's CONVERSION TO THE IMPROVED STANDARD TECHNICAL SPECIFICATIONS (TAC N M98738)
REFERENCES: (1) WCNOC letter dated December 17,1998, response to Q3.8.4-17 ,
(2) NRC Inspection Report 50-482/97-201 dated February 23,1998, inspector Follow-up items 482/37-201-08 and -09 On February 12,1999, a meeting was held between Wolf Creek Nuclear Operating Corporation (WCNO_C) personnel and the Nuclear Regulatory Commission (NRC) staff to discuss a !
proposed change to the Wolf Creek Generating Station battery technical specification j Attachment 1 lists the attendees. The slides presented by WCNOC are provided in Attachment 2. Also included in Attachment 2 is a vendor letter dated June 10,1998, provided to the staff at the meetin The proposed change is the following:
Revise current technical specification (CTS) surveillance requirement (SR) 4.8.2. battery capacity acceptance criteria from 80% to 85% of manufacturer's ratin This proposed change was made by WCNOC in Reference 1 as a result of a recent plant modification that replaced the Gould manufactured square cell batteries with round cell ,
batteries (Reference 2). This proposed change is presented as issue #1 in the attached WCNOC slides. The proposed change is considered to be a beyond scope issue (BSI)
relative to the approval of the improved Technical Specifications (ITS), since the requirement is different than both the CTS for Wolf Creek Generating Station and the standard ITS, as provided in NUREG-1431, " Standard Technical Specifications for Westinghouse Plants,"
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Considering the recent round cell battery modification, the NRC staff also discussed two requirements in the Wolf Creek Generating Station CTS and whether they should be revised as part of the conversion to the ITS. These two CTS requirements are as follows: 7 L
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9904050044 990330 l PDR ADOCK 05000482 l G PDR \
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- Wolf Creek CTS SR 4.8.2.1.f includes a frequency of 18 months. The staff questioned whether this frequency should be revised to 12 months, as provided in the ISTS. This is issue #2 in the attached WCNOC slide . Wolf Creek CTS SR 4.8.2.1.f defines battery degradation as being indicated "when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests..." The staff questioned whether it would be more technically appropriate to use the last performance test results instead of the average of the previous performance tests. This is issue #3 in the attached WCNOC slide
These three issues were discussed at the meeting. For each issue, the following conclusions were reached; ;
l issue #1 - The staff considers the technical basis for revising the current technical j specification (CTS) surveillance requirement (SR) 4.8.2.1.e battery capacity l acceptance criteria from 80% to 85% of manufacturer's rating to be acceptabl '
WCNOC committed to verify that procedures for this surveillance test will ensure that abnormal test results would be included in the WCNOC corrective action program, even if the SR acceptance criteria are met. WCNOC also confirmed that their commitment to perform additional capacity testing, as described in Reference 1, remains unchange )
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issue #2 - The SR 4.8.2.1.f frequency of 18 months in the CTS, which was previously j approved by the staff, is consistent with that recently approved on other plant 1 conversions to the ISTS and will be maintaine j issue #3 - In their conversion to the ITS, WCNOC agreed to revise the CTS SR 4.8.2. definition of battery degradation from being based on the average of previous
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performance tests to being based on the last battery performance test result Accordingly, WCNOC will revise their response to NRC staff question Q3.8.4-17 (Reference 1) to reflect thi Subsequent to the discussion on the battery technical specifications, WCNOC personnel discussed their responses to the staff's requests for additional information (RAls) on ITS
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Section 3.8 dated September 3 and October 7,1998. The licensee's responses to the RAls were provided in its submittal dated December 17,1998. The staff's questions on the
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-3- March 30, 1999 licensee's responses are listed in Attachment 3. These questions were discussed with the licensee. Any corrections to the licensee's responses for ITS Section 3.8 will be documented in future submittals to the staf ORIG. SIGNED BY Mel Gray, Project Manager Project Directorate IV-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-482 DISTRIBUTION: (Hard copy)
D00hntRW3 Attachments: 1. List of Meeting Attendees PUBLIC 2. .WCNOC Slides and Vendor Letter PDIV-2 Reading 3. List of Questions on ITS Section .ACRS OGC cc w/atts: See next page MGray !
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KThomas DISTRIBUTION: (e-mail)
SCollins/RZimmerman BSheron JZwolinski/SBlack
WBateman EPeyton JKnox TLe ETomlinson SSaba JDonohew JCalvo Karockman, Region IV LYandell, Region IV DLange, EDO Document Name: Mts98738.WPD OFC PDIV-2/PM PDIV-2/LA PDIV NRR/EELB NAME N EP N JDon JCalvo /)k DATE 1/ /P/99 3 /l1 /99 3 // 7/99 3 /3o/99 )
OFFICIAL RECORD COPY l l
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licensee's responses are listed in Attachment 3. These questions were discussed with the ,
licensee. Any corrections to the licensee's responses for ITS Section 3.8 will be documented in future submittals to the staff, h
Mel Gray, Project Manager Project Directorate IV-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-482 Attachments: 1. List of Meeting Attendees ,
2. WCNOC Slides and Vendor Letter 3. List of Questions on ITS Section cc w/atts: See next page l
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Jay Silberg, Es Chief Operating Officer Shaw, Pittman, Potta & Trowbridge Wolf Creek Nuclear Operating Corporation 2300 N Street, NW P. O. Box 411 Washington, D.C. 20037 Burlington, Kansas 66839 Regional Administrator, Region IV Supervisor Licensing U.S. Nuclear Regulatory Commission Wolf Creek Nuclear Operating Corporation 611 Ryan Plaza Drive, Suite 1000 P.O. Box 411 Arlington, Texas 76011 Burlington, Kansas 66839 Senior Resident inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident inspectors Office P. O. Box 311 8201 NRC Road Burlington, Kansas 66839 Steedman, Missouri 65077-1032 Chief Engineer Mr. Otto L. Maynard Utilities Division President and Chief Executive Officer
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Kansas Corporation Commission Wolf Creek Nuclear Operating Corporation
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1500 SW Arrowhead Road Post Office Box 411 Topeka, Kansas 66604-4027_ Burlington, Xansas f4839 Office of the Governor State of Kansas Topeka, Kansas 66612 Attomey General Judicial Center 301 S.W.10th 2nd Floor Topeka, Kansas 66612 County Clerk Coffey County Courthouse Burlington. Kansas 66839
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Vick L. Cooper, Chief Radiation Control Program Kansas Department of Health and Environment -
Bureau of Air and Radiation Forbes Field Building 283 Topeka, Kansas 66620
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Attachment 1 MEETING WITH WOLF CREEK NUCLEAR OPERATING CORPORATION LIST OF MEETING ATTENDEES February 12,1N WOLF CREEK NUCLEAR OPERATING CORPORATION T. Harris R. Muench K. Fullen L. Solorio S. Wideman J. Anderson (Wyle Labs, attending with WCNOC)
NBC M. Gray B. Bateman C. Posiusny J. Knox T. Le E. Tomlinson S.Saba J.Donohew J. Calvo
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Lucent Technologies Bell 1. abs Innovations U 3000 skyhne Drive Mesquite. TX 75849 Mr. James W. Anderson, June 10,1998 Telephone M4 284 2000 Wyle Laboratories Th Scientific and Systems Group 7800 Highway 20 West Huntsville AL 35806 Sub: Round Cell replacemen* riteria Ref: Your letter to M. Weeks dated May 18,199 The Lineage 2000 Round Cell is a pasted plate lead acid battery with unique features designed to significantly increase float life, reduce maintenance and increase safety in applications oflong term float service and infrequent discharges. The electrochemistry av failure mechanisms of the Round Cell are similar to other pasted plate lead-acid designs. The Round Cell design was designed to eliminate capacity loss due to positive grid corrosion which is one of the primary failure modes for conventional rectangular cells. However, reduced capacity can occur due to other causes like excessive cycling etc.,
As stated earlier, the Round Cell is a pasted plate lead-acid batten subject to sunilar failure mechanisms as other pasted plate lead acid designs. Therefore, from a battery performance point of view, Lucent Technologies reconunerxis the same 80% of rated capacity replacement criteria commonly used throughout the lead-acid battery industr vb Dr. K. A. Murugesamoorthi Ph.D.,
Portfolio Manager Copy to:
F. Geosits G. Jarrett F. Imman C. Mak K. Mortazavi M. Weeks
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. .o Attachment 3 WOLF CREEK ITS SECTION 3.8 ITEMS FOR DICUSEl,QN Q3.8.G.1: Page B 3.8-61: 3rd paragraph: Degradation of 10% for rectangular vs round cells? WC to correct after meeting with Saba on Friday.-
Page B 3.8-70: SR 3.8.6.2: Are the new 110V and 150V numbers part of CTS? If not explain its source . Q3.8.1-12: Regarding item (2), how was this separation and independent controlled if not in LCO? Q3.8.1-14: Licensee needs to explain the following: "the proper condition to perform its safety function may be considered OPERABLE." Q3.8.1-15: The licensee needs to explain how it has answered the questio . Q3.0-1-17: The licensee needs to explain new DOC 3.8.50 Why CTS requirements j
- can provide an acceptable means of demonstrating DG operability? Also how will WCNOC adopt Comanche Peak's revised response to this same question? J l
1 Q3.8.2-01: Regarding the 2nd train issue: The licensee needs to follow the revised response from the Comanche Peak latest versio . Q3.8.2-04: CTS page 3/48-8: There are missing words for 3.8.1.2 b. How does this work if a second train is required (2nd train issue) Q3.8.2-06: The licensee needs to explain the 2nd train issu . Q3.8.3'-05: NUREG markup page 3.8-23: The licensee needs to explain how it handles Condition E of the actions and when are two air receivers checked vs one is checked?
1 Q3.8.3-09: When does the licensee test for this automatic makeup supply?
1 Q3.8.4-08: The modified performance test (MPT) profile has not been submitte When willit be available? Does the licensee understand the staff's position regarding the MPT profile?
1 Q3.8.4-09: Is the licensee planning to adopt wordings from the Comanche Peak latest changes? In the Bases and elsewhere?
1 Q3.8.4-17: This is the open item regarding 85 or 95 percent of capacity degradatio See meeting minutes in this documen . Q3.8.4- 29: The licensee's response was not entirely adequate. Was the cable drop a )
consideration in this value change? Has the licensee referred to the voltage cal drop to ensure operability of remotest equipment / devices?
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-2-1 _ Q3.8-10-01: Regarding the 2nd train issue, the licensee needs to explain how they will revise the Base . Q3.8.10-02: Regarding the 2nd train issue, the licensee needs to explain how the Bases for LCO 3.8.10 will be revised to agree with Comanche Peak's latest change Will JFD 3.8-45 and DOC 03.06-LS also be revised?
1 Q3.8.10-03: Regarding the 2nd train issue, DOC 03.03-LS needs to be improved. The note says that the action is to be revised. Has it been revised because it was not submitted with the response?
1 Q3.8-10-05: Regarding the 2nd train issue, the licensee needs to discuss how the Bases are to be revised to adopt Comanche Peak's corresponding Base . Q3.8.10-04: The licensee has not explained their answe . Q3.8.B.04.d: The staff does not understand the respons . Q3.8.B.04.f:: The staff does not understand the response. The staff needs more information regarding the phrase "only one offsite source is required to be available..."
2 Q3.8.B.04.l: Related to TSTF 283, is there any revision to the Bases?
2 Q3.8.B.04.k, 04.1, 04.s: Regarding the two trains issue, the licensee needs to revise the Bases in a manner similar to that done for Comanche Pea . - Q3.8.B.04.t: The licensee needs to explain their answe . Q3.8B.04.v. 04.w,04.z: The licensee needs to explain its response. Are any further revisions to the Bases needed?
WC 3.8-003: The licensee should revise the Bases to reflect that the intent of the SR is
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2 also to verify that the critical trips could trip the diesel generato . Is there an attachment such as WC 3.8.005 to the licensee's response submittal?
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