ML20137A379

Summary of 970212 Meeting W/Wolf Creek Nuclear Operating Corp to Discuss Status of Licensing Actions Currently Under Review by NRR Staff & to Discuss Upcoming Requests Identified by Licensee

ML20137A379
Person / Time
Site:	Wolf Creek
Issue date:	03/17/1997
From:	Stone J NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
GL-91-08, GL-91-8, GL-93-05, GL-93-5, TAC-89161, TAC-91859, TAC-91899, TAC-93381, TAC-97361, TAC-97362, NUDOCS 9703200303
Download: ML20137A379 (6)

Text

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j UNITED STATES NUCLEAR REGULATORY COMMISSION t WASHINGTON, D.C. 2061 6 0001

/ March 17,1997 J

LICENSEE

Wolf Creek Nuclear Operating Corporation FACILITY: Wolf Creek Generating Station 1

SUBJECT:

STATUS OF OUTSTANDING LICENSING ACTIONS AND UPCOMING REQUESTS Backaround:

y On February 12, 1997, I met with members of the Wolf Creek Nuclear Operating _

Corporation's staff to discuss the status of licensing actions currently under  !

review by the NRR staff and to discuss any upcoming requests the licensee has i identified. This meeting was at the Wolf Creek site. I lummary:

1. The status of the following amendment requests was discussed:

a. ECCS Accumulator Allowed Outage Time (TAC M91859) )

1 This amendment would increase the allowed outage time (A0T) for an ECCS accumulator from I hour to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for conditions other than boron concentration outside the allowable band and would add a new action statement that would allow 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to return the boron concentration in the accumulator to within the allowable band.

The 72-hour A0T for boron concentration is in accordance with Generic Letter 93-05. The 24-hour A0T is based on a risk argument,

' supplemented with administrative controls to ensure key safety systems are in service prior to removing the accumulator from

service. This amendment request is being held, pending completion of the staff's review of the topical report submitted by Combustion Engineering. The licensee noted that the ITS submittal is being prepared on the assumption that this has been approved.

b. Relocation of Containment Isolation Valve Tables (TAC M91899)

This amendment would relocate the containment isolation valve tables from the technical specifications to the Final Safety Analysis Report (FSAR). A supplement has been received from the licensee that deletes a proposed footnote that would have increased the A0T from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the reactor coolant pump seals supply

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and return line isolation valves. This amendment request is now in accordance with Generic Letter 91-08.

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goos, NBC HIR CENTER COPY 9703200303 970317 PDR ADOCK 05000482 P PDR

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. c. Change in Action Statement for the Refueling Water Storage Tank (TAC l

! M97361)

! 'This amendment would' change the action statement to be followed in 1

case of a failure of the RWST level instrument. A request for additional information was issued by the staff on January 21, 1997.

The, licensee 1s withdrawing this request.  !

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! d. Change -in the Inspection Method of the Reactor Coolant Pump Flywheel i i- (TAC M97362) 'l

i.  !

L This request would change the inspection method for the reactor i 2

coolant flywheel to allow either a surface examination or an i t ultrasonic examination. The staff is currently reviewing this i request. Additional information will be required in order for the i staff to complete its review.

2. The status of the following licensing activities was discussed:

a. Exemption from 10 CFR 70.24, Criticality Monitors (TAC M89161) )

l This would exempt the licensee from the requirements to have l criticality accident monitors in the spent fuel and new fuel storage areas. On January 30, 1997, the staff issued a request for ]l additional information with a requested response time of 45 days.

b.- Second Ten Year' Inservice Inspection Program Plan (TAC M93381) l The plan is still undergoing staff review. Subsequent to the  !

meeting, a fourth request for additional information was issued by I the staff. This RAI has a requested response time of 60 days from .

the date of receipt of the RAI. l l

3. The licensee has identified the following items to be submitted for approval:

a. The next core will use ZIRLO cladding. The TS will have to be changed to allow the use of ZIRLO.

b. A change to TS 3.9.4 to allow the opening of steam generator drain valves while fuel movement is in progress will be proposed. The ,

valves are manual and proposal will be to station dedicated personnel to close the valve, if required, in lieu of automatic action, as required by the current TS.

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c. A change to TS 4.5.2.c.2.to allow the inspection of the containment on a daily basis. The current TS requires a containment inspection aner each entry.

A list of personnel that attended the meeting is attached.

Original Signed By James C. Stone, Senior Project Manager Project Directorate IV-2 l Division of Reactor Projects III/IV '

Office of Nuclear Reactor Regulation Docket No. 50-482 DISTRIBUTION: (Hard Copy)  !

Docket File PDIV-2 Reading l

Attachment:

Attendee List PUBLIC JStone I cc w/att: See next page E-mail ,

SCollins (SJCl) i FMiraglia (FJM) ~

AThadani (ACT) l RZimmerman (RPZ)

JRoe (JWR)

EAdensam (EGAl)

WBateman (WHB)

EPeyton (ESP)

EHackett, ED0 (EMHl)

MBiamonte (MAB)

AHowell, RIV l

1 DOCUMENT NAME: 212 MEET.WC 0FC PDIV-2/PM _ PDIV-2/LA l' NAME JStone:yh EPettfF DATE 3////97 3/l7/97 0FFICIAL RECORD COPY

l 1

1 p c. A change to TS 4.5.2.c.2 to allow the inspection of the containment l

on a daily basis. The current TS requires a containment inspection l after each entry.

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l A list of personnel that attended the meeting is attached.

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[ dM James C. Stone, Senior Project Manager Project Directorate IV-2

! Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

! Docket No. 50-482 i

Attachment:

Attendee List 4

cc w/att: See next page i

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Jay Silberg, Esq. Chief Operating Officer Shaw, Pittman,.Potts & Trowbridge Wolf Creek Nuclear Operating Corporation 2300 N. Street, NW .P. O. Box 411 l Wuhington, D.C. 20037 Burlington, Kansas 66839 Regional Administrator, Region IV Supervisor Licensing U.S. Nuclear Regulatory Comission Wolf Creek Nuclear Operating Corporation i 611 Ryan Plaza Drive, Suite 1000 P.O. Box 411

Arlington, Texas 76011 Burlington, Kansas 66839 i Senior Resident Inspector U.S. Nuclear Regulatory Comission j - U.S. Nuclear Regulatory Comission 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 Kansas Corporation Comission Wolf Creek Nuclear Operating Corporation 1500 SW Arrowhead Road Post Office Box 411

! Topeka, Kansas 66604-4027 Burlington, Kansas 66839 i Office of the Governor State of Kansas Topeka, Kansas 66612 l Attorney General

- Judicial Center 301 S.W. 10th 2nd Floor j

Topeka, Kansas 66612 i County Clerk 3

Coffey County Courthouse Burlington, Kansas 66839 Public Health Physicist

. Bureau of Air & Radiation l Division of Environment

. Kansas Department of Health and Environment i Forbes Field Building 283 Topeka, Kansas 66620

.' Attachment 1 MEETING WITH WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK LICENSING ACTIONS ATTENDEES February 12. 1997 Wolf Creek Nuclear Operatina Corporation Terry Damashek Steve Wideman Kansas Deoartment of Health and Environment Ron Fraass EE

' James Stone

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