ML20148P096

Summary of 970603 Meeting W/Wcnoc Staff to Discuss Status of Licensing Actions Currently Under Review by NRR & to Discuss Any Upcoming Requests That Licensee Has Identified

ML20148P096
Person / Time
Site:	Wolf Creek
Issue date:	06/25/1997
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-M89161, TAC-M91859, TAC-M91899, TAC-M93381, TAC-M97362, TAC-M97682, TAC-M97883, TAC-M98204, TAC-M98506, TAC-M98507, TAC-M98508, TAC-M98738, TAC-M98809, NUDOCS 9707010213
Download: ML20148P096 (6)

Text

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pnuc p* oq\ UNITED STATES j

g NUCLEAR REGULATORY COMMISSION {

WASHINGTON D.C. 20555 4 001 j June 25, 1997 i *****

l LICENSEE: Wolf Creek Nuclear Operating Corporation  !

', FACILITY: Wolf Creek Generating Station

SUBJECT:

STATUS OF OUTSTANDING LICENSING ACTIONS AND UPCOMING REQUESTS l i

Backaround On June 3.1997. I met with members of the Wolf Creek Nuclear Operating Corporation's (WCNOC) staff to discuss the status of licensing actions currently under review by the NRR staff and to discuss any upcoming requests the licensee has identified. This meeting was held at the Wolf Creek site.

Summary

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

)

a. ECCS Accumulator Allowed Outage Time (TAC M91859)

This amendment would increase the allowed outage time (A0T) for an ECCS accumulator from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 wouhl 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 baced on a risk argument.

supplemented with administrative controls to ensure key safety systems are in service prior to removing the accumulator from service. A similar request for Combustion Engineering plants is .

being reviewed by the staff. The staff is reviewing the Wolf Creek request. The' licensee has submitted the request for the improved standard technical specifications which assumes that this amendment request has been approved. -

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

This amendment would remove the containment isolation valve tables from the technical specifications to a licensee controlled document.  ;

This amendment request is in accordance with Generic Letter 91-08(

The request has been ^ wed and the amend n t package has been prepared.

c. Change in the In ;thod 'of tv ar Coolant Pump Flywheel (TAC M97362)/

This request would c. method for the reactor coolant pump (RCP) fly . .ther a surface examination of ,

9707010213 970625 PDR ADOCK 05000482 Md 7 ME CEMER CM k yd ft P PDR u

l an ultrasonic examination and also change the frequency of the l examination. For the "D" RCP a one time extension of the inspection ;

interval has been included. The amendment will be issued during the '

< week of June 23. 1997,

d. UseofZIRLOCladFuel(TACM98204f  ;

This amendment would allow the use of ZIRLO clad fuel. The staff is reviewing this request. A supplement may be required to add the Westinghouse topical to the list of methodologies referenced in the technical specifications for use in determining limits in the Core Operating Limits Re) ort. Approval has been requested before the i start of the Septem)er 20. 1997. refueling outage.

c. Containment Penetration Control During Refueling '(TAC M98508[

This request would allow the breathing air and service air

, containment penetrations to remain open under administrative controls, during fuel movement. This amendment will be issued during the week of July 7.1997,

d. Conversion to the Improved Standard Technical Specifications (TAC M98738V  !

This amendment would convert to the new improved standard technical specifications and was arepared in concert with Callaway. Diablo '

Canyon and Comanche Pea (. This application has just been received.

, Staff review has not started pending receipt of the Diablo Canyon I

application.

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

criticality accident monitors in the new fuel storage area and conduct emergency drills in response to the alarms. Additional information has been received and the issue is currently under staff

, review.

b. Second Ten Year Inservice Inspection Program Plan (TAC M93381I l The response to the fourth request for additional information has l been received. The staff is reviewing the submittal.

c. UseofCodeCaseN-508-1(TACM97682f The staff has completed their review of this request. The approval to use this case is expected to be issued by the end of June 1997.

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d. Inservice Test Program Relief Request 2VR-7 & 8 (TAC M97883)/

The first relief request (2VR-7) proposes to use Code Case OMN-1,

'" Alternative Rules for Preservice and Inservice Testing of'Certain Electric Motor-Operated Valve Assemblies in Light-Water Reactor-Power Plants OM Code-1995 Subsection ISTC," for testing of motor operated valves. The second relief request (2VR-8) proposes to use ASME OMa-1996. Subsection ISTC 4.5 including the Mandatory Appendix II, " Check Valve Condition Monitoring Program," as an alternative to the current check valve test program. The staff is currently reviewing this application. A supplement.will be required to provide additional information that was requested in order for the staff to complete its review. ~

e. InserviceTestProgramReliefRequest2VR-9(TAC.M98506f

-This request proposes an alternative test method for a check valve that is a containment isolation valve. The leak test and operational test would be done at 5-year intervals. The staff is reviewing the request,

f. Inservice Inspection Program Relief Request 12R-22 (TAC M98507)

This request proposes to use a later edition ofsthe code for the i inspection of buried pipe. The staff has requested additional information about-the acceptable leak rates'and inspection techniques available to determine the leak location.

g. Inservice Inspection Pro ram Relief Requests 11R-46 through IIR-49 ,

and 12R-21 (TAC M98809)

These relief requests provide the results of previous examination activities during Refuel VI and Refuel VII. with supplemental examinations completed during-Refuel VIII. The staff has requested additional information from the licensee.

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

a. The following submittals were identified by the licensee with approval ~ desired before the end of the next refueling outage (October 20, 1997):

j e- Elimination of pressure sensor time res)onse testing- ,

requirements as detailed in WCAP-13632 3-A, Revision 2.

e A revised definition of core alteration, The licensee is considering using the definition in the Improved Standard Technical Specifications.

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i e - Revise Action 5.a. of Table 3.3-1 to clearly define actions to be taken on loss of a source range channel during. Mode 3.

4. or 5.

The licensee was reminded that the' sooner the applications were submitted. the more likely approval could be obtained by the

j. ' requested date.

! b. Clarify the action statements for auxiliary feedwater system

. depending on the availability of different combinations of essential

i service water supplies to the auxiliary feedwater pumps and the "

availability of different steam supplies to the turbine driven pump. ,

c. Change the titles of the operating crews.

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d. Replace the corrective action request (CAR) program with the  ;

performance improvement request in the QA program. '

j. e. Revision to the emergency plan to convert to the administrative procedure format.

2.

l Personnel in attendance at the meeting were James Stone. NRC. Terry Damashek.

WCNOC. and David Claridge. WCNOC.

i i James C. Stone. Senior Project Manager

Project Directorate IV-2 Division of Reactor Projects III/IV 5

Office of Nuclear Reactor Regulation Docket No. 50-482

cc

See next page b'

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e .

L:

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e Revise Action 5.a. of Table 3.3-1 to clearly define actions

' to be.taken on loss of a source range channel during Mode 3, 4, or 5.  :

The licensee was reminded that.the sooner the applications were submitted, the more likely approval could be obtained by the' requested date. >

, b. Clarify the action statements for auxiliary feedwater system depending on the availability of different combinations of essential l service water supplies to the auxiliary feedwater pumps and the ,

l availability of different steam supplies to the turbine driven pump. '

c. Change'the titles of the operating crews.

L .

d. Replace the corrective action request (CAR) program with the' performance improvement request in the 0A program,

e. Revision to the emergency pla'n to convert to the administrative procedure format.  ;

l Personnel in attendance at the meeting were James Stone. NRC. Terry Damashek.  !

j WCNDC. and David Claridge. WCNOC. I

j. Original . Signed By James C. Stone.. Senior Project Manager ,

i Project Directorate-IV-2 l

! Division of Reactor. Projects III/IV i l Office of Nuclear Reactor Regulation l Docket No. 50-482 DISTRIBUTION: (Hard Copy)  ;

l Docket File PDIV-2 Reading cc: See next page PUBLIC OGC ACRS

E-Mail S. Collins (SJC1)

F. Miraglia (FJM)

R. Zimmerman (RPZ)

J. Roe (JWR)

W. Bateman (WHB)

L J. Stone (JCS3) l E. Peyton (ESP) '

l D. Ross'(SLM3) i M. Dapas. EDO A. Howell RIV DOCUMENT NAME: 63 MEET.WC i 0FC PDIV-2/PGJ( PDIV-2/LA

{ NAME JStone:y$ Efsyt%

DATE 6//f/97 6S3/97 0FFICIAL RECORD COPY c

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cc:

Jay Silberg, Esq. Chief Operating Officer Shaw, Pittman, Potts & Trowbridge Wolf Creek Nuclear Operating Corporation 2300 N Street, NW P. O. Box 411 l Washington, D.C. 20037 Burlington, Kansas 66839 l Regional Administrator, Region IV Supervisor Licensing U.S. Nuclear Regulatory Comission Wolf Creek Nuclear Operating Corporation l 611 Ryan Plaza Drive, Suite 1000 P.O. Box 411 1 Arlington, Texas 76011 Burlington, Kansas 66839 l Senior Resident Inspector U.S. Nuclear Regulatory Commission 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 Commission Wolf Creek Nuclear Operating Corporation 1500 SW Arrowhead Road Post Office Box 411 Topeka, Kansas 66604-4027 Burlington, Kansas 66839 ,

Office of the Governor State of Kansas Topeka, Kansas 66612 Attorney General Judicial Center 301 S.W. 10th 2nd Floor Topeka, Kansas 66612 county Clerk Coffey County Courthouse Burlington, Kansas 66839 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