ML20206G237

Summary of 990414 Meeting with NYPA in Rockville,Md Re Proposed Improved TSs for Plant,Which Was Submitted on 990331.List of Attendees & Handouts Provided by NYPA Encl

ML20206G237
Person / Time
Site:	FitzPatrick
Issue date:	05/04/1999
From:	Williams J NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
TAC-MA5049, NUDOCS 9905070136
Download: ML20206G237 (13)

Text

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p 4 UNITED STATES s* j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.c. 20556 0001

%..... N y 4, 1999 LICENSEE: New York Power Authority l FACILITY: James A. FitzPatrick Nuclear Power Plant

SUMMARY

OF APRIL 14,1999, MEETING REGARDING PROPOSED IMPROVED TECHNICAL SPECIFICATIONS (TAC NO. MA5049)

On April 14,1999, representatives of the New York Power Authority (NYPA) met with members of the NRC staff in Rockville, Maryland. NYPA had requested this meeting in order to brief the NRC staff on the content and implementation schedule of the proposed improved Technical Specifications (ITS) for the James A. FitzPatrick Nuclear Power Plant, which were submitted ,

on March 31,1999. A list of attendees is provided in Enclosure 1. A copy of the handouts provided by NYPA is provided in Enclosure 2.

NYPA provided a list of the ITS items which they consider to be beyond the current Technical )

Specifications (CTS) and outside the standard ITS. Such changes are referred to as "beyond-scope" changes. NYPA identified 13 items as beyond-scope items. The bulk of the iTS conversion is reviewed by the NRC Technical Specification Branch and/or its contractors.  !

However, beyond scope changes are treated similar to conventional license amendment

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requests, where the Project Manager (PM) coordinates review with the responsible technical '

branches.

The participants discussed the review and implementation schedule. The licensee expects to {

request that imolementation be completed after the refueling outage in fall 2000, so that the

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outage can be planned based upon the CTS The licensee believes this implementation j schedule will reduce their uncertainty regarding the outage ground rules. Based on the current l

ared projected ITS work load, the staff believes that the FitzPatrick ITS can be completed several months ahead of the licensee's implementation schedule. The participants recognized that a long interval between the completion of NRC review and licensee implementation could 1 result in some issues which would have to be coordinated between the CTS and ITS. The )

consensus was that any problems could be minimized with proper planning. The licensee will document its proposed implementation schedule in a Inter to the staff in the near future.

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The participants also discussed the coordination of CTS changas with the ITS content. The ITS submittal was developed assuming that all pending license amendments are issued in a form consistent with the individual amendment submittals. However, there is some potential i for changes in the individual submittals which would affect the ITS content, as for the pending amendments regarding spent fuel pool capacity and emergency diesel generator allowed outage time. The staff expressed an inWest in comparing the ITS to the existing CTS. The PM will make available copies of pending amendments for the use of the NRC reviewers. The 1

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9905070136 990504 PDR ADOCK 05000333 P PDR l

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l l licensee was also encouraged to carefully evaluate the need for any additional amendments against the potential impact on the ITS conversion.

l It was agreed that questions would be forwarded to the licensee on an informal basis as soon as pcssible, and that follow up telephone discussions would be conducted to resolve as many items as possible prior to issuance of a formal request for additional information.

h ,

oseph F. Williams, Project Manager, Section 1 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosures:

1. List of Attendees

2. Handouts cc w/encls: See next page i

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t licensee was also encouraged to. carefully evaluate the need for any additional amendments against the potential impact on the ITS conversion,

j. :it was agreed that questions would be forwarded to the licensee on an informal basis as soon as possible, and that follow up telephone discussions would be conducted to resolve as many items as possible prior to issuance of a formal request for additional information.

I' Original signed by:

l t Joseph F. Williams, Project Manager, Section 1 )

l Project Directorate l l l Division of Licensing Project Management Cihce of Nuclear Reactor Regulation

. Docket No. 50-333 l )

t

Enclosures:

1. List of Attendees l 2. Handouts l l .

1 cc w/encis: See next page -

i DISTRIBUTION: See next page

, DOCUMENT NAME: G:\FITZ\MTS0549.WPD

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l .To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" = copy with l tttachment/ enclosure "Na = ho copy .

'h0FFICE PDla1/PM M ', [__ PDI 1/ LAM L l PDI-1/SC , l l lNAME JWilliamstic M SLittle V $8aJwa M A '

EDATE 05/ P/99 // 05/ 't /99 05/Q /99 05/ /99 OFFICIAL RECORD COPY l

% .z _. 1 Fby 4,1999

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l licensee was also encouraged to . carefully evaluate the need for any additional amendments l against the potential impact on the ITS conversion, it was agreed that questions would be forwarded to the licensee on an informal basis as soon as possible, and that follow up telephone discussions would be conducted to resolve as many items as possible prior to issuance of a formal request for additional information.

Original signed by:

o Joseph F. Williams, Project Manager, Section 1 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-333 l

Enclosures:

1.' List of Attendees

2. Handouts 1

cc w/encls: See next page DISTRIBUTION: See next page DOCUMENT NAME: G:\FITZ\MTS0549.WPD i l

Te receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" a copy with i attachment / enc losure "N" a No copy ,.

OFFICE P01 1/PM M, l P01 1/ LAM L l P01 1/$C , l i NAME JWIi t Iano s t cM Slit tleV $Bajwa Md DATE 05/ P /99 // 05/ 4 /99 05/Q /99 ' 05/ /99 OFFICIAL RECORD COPY l

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I Meeting Summary Distribution:

LICENSEE: New York Power Authority FACILITY: James A. FitzPatrick Nuclear Power Plant

SUMMARY

OF APRIL 14,1999, MEETING REGARDING PROPOSED IMPROVED TECHNICAL SPECIFICATIONS (TAC NO. MA5049) l E-Mail (w/ encl.1) Hard Copy (w/all encls.)

J. Zwolinski/S. Balck Docket File S. Bajwa PUBLIC S. Little PDI-1 R/F W. Beckner J. Williams J. Luehman OGC B. Denning ACRS M. Weston B Tjader cc: Licensee & Service List T.Le A. Blough, Region i D. Screnci, Region I l

Meeting Summary Distribution:

LICENSEE: New York Power Authority FACILITY: James A. FitzPatrick Nuclear Power Plant

SUMMARY

OF APRIL 14,1999, MEETING REGARDING PROPOSED IMPROVED TECHNICAL SPECIFICATIONS (TAC NO. MA5049)

E-Mail (w/ encl.1) Hard Coov (w/all encis.) i i

I J. Zwoiinski/S. Balck %BibilliiEMI3 S. Bajwa PUBLIC S. Little PDI-1 R/F ,

W. Beckner J. Williams l J. Luehman OGC j

, B. Denning ACRS M. Weston B Tjader cc: Licensee & Service List T.Le-A. Bicugh, Region 1 D. Screnci, Region l l

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070022 l

e l James A. FitzPatrick Nuclear Power Plant Mr. Gerald C. Goldstein Mr. F. William Valentino, President Assistant General Counsel New York State Energy, Research, j Power Authority of the State and Development Authority of New York Corporate Plaza West 1633 Broadway 286 Washington Avenue Extension New York, NY 10019 Albany, NY 12203-6399 Resident inspector's Office Mr. James Knubel U. S. Nuclear Regulatory Commission Chief Nuclear Officer P.O. Box 136 Power Authority of the State of Lycoming, NY 13093 New York -

123 Main Street Mr. Harry P. Salmon, Jr. White Plains, NY 10601 I Vice President- Engineering i Power Authority of the State Mr. Richard L. Patch, Director l of New York Quality Assurance l 123 Main Street Power Authority of the State {

White Plains, NY 10601 of NewYork i 123 Main Street l Ms. Chariene D. Faison White Plains, NY 10601 l Director Nuclear Licensing i Power Authority of the State Mr. Gerard Goering j of New York 28112 Bayview Diive ,

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123 Main Street Red Wing, MN 55066 White Plains, NY 10601 Mr. James Gagliardo Supmisor Safety Review Comittee Town of Scriba 708 Castlewood Avenue Route 8, Box 382 Arlington, TX 76012 Oswego, NY 13128 Mr. Arthur Zaremba, Licensing Manager Mr. Eugene W. Zeitmann James A. FitzPatrick Nuclear President and Chief Operating Power Plant Officer P.O. Box 41 Power Authority of the State Lycoming, NY 13093 of New York 99 Washington, Ave., Suite No. 2005 Mr. Paul Eddy Albany, NY 12210-2820 New York State Dept. of Public Service Charles Donaldson, Esquire 3 empire State Piaza,10th Floor Assistant Attorney General Albany, NY 12223 New York Department of Law 120 Broadway Michael J. Colomb New York, NY 10271 Site Executive Officer James A. FitzPatrick Nuclear Power Plant Regional Administrator, Region l P.O. Box 41 U.S. Nuclear Regulatory Commission Lycoming, NY 13093 475 Allendale Road King of Prussia, PA 19406

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- Attendees NRC/NYPA Meeting l

- FitzPatrick Improved Technical Specifications April 14,1999 Name Affiliation 1

l Bill Beckner NRR/RTS8 1 Jim Luehman NRR/RTSB Bob Dennig NRR/RTSB Maggalean Weston- - NRR/RTSB Bob Tjader NRR/RTSB Tommy Le NRR/RTSB Joe Williams NRR/PD I John Kelly NYPA Jack Gray NYPA Verne Childs NYPA Bob Steigerwald NYPA 1

Enclosure 1

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FITZPATRICK IMPROVED TECHNICAL SPECIFICATION STATISTICS ,

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Improved Technical Specifications

+ 118 Specifications

+ 1028 total pages (Specifications & Bases) p pht/h )

+ 337 Specification pages

+ 691 Bases pages l 0

Technical Specification Changes

+ 775 total changes (approximately) l

+ 300 more restrictive

+ 290 less restrictive l

+ 185 relocated

+ 13 changes "Beyond CTS & Beyond ISTS"  ;

ITS Submittal

+ 8890 total pages

+ 250 tabs

+ 1200 divider pages

+ 40 contents pages

+ 7400 pages of technicalinformation

+ 19 volumes per controlled copy

+ 116 pounds per controlled copy ITS Distribution 1 + 25 controlled copies

+ 222,250 total pages Enclosure 2

, ;-, E Additions to Attachment 3 JPN 99 008 NYPA Transmittal NYPA Serial Number JPTS TAC Number ~ And Date Number JPTS Title M99824 JPN 97 033 96 012 Design Features 10/14/97 JPN 98 033 Response to written request for 07/23/98 additional information dated 6/1/98 JAFP 98 0385 Revision to proposed change 12/03/98 regarding Design Features j JPN 99 005 Response to written request for 02/25/99 additional information dated 1/26/99 JAFP 99 0127 Affidavit to support proposed change 04/08/99 regarding Design Features

,MA4591 JPN 99 002 99 001 LPRM Calibration I JPN 99 011 99 002 Administrative Controit I un a _

If ' - Revised Attachment 3 JPN 99 008 l TAC NggN NYPA JPTS JPTS Title Number and Date Number M99751 J 7 32 JPTS 97 004 Distribution of Inoperable Control Rods

'MA1136 Jggg7 JPTS 97 007 Revision to SGT Charcoal Efficiency and Change for Increasing Allowable Containment Leakage (L.)

M94611 Jg6g4 JPTS 95 007 Emergency Diesel Generator Allowable Out-of service Time Jy;gg8 Response to written Request for Additional Information dated 4/18/96 JPN 96 038 Response to verbal Request for Additional 09/12/96 Information dated 6/17/96 JPN 97-012 Response to written Request for Additional 03/17/97 Information dated 2/4/97 JPN 97 027 Response to verbal Request for Additional 09/09/97 Information dated 9/3/97 H95521 Jgg3 JPTS 95 005 Fire Protection Procedure Review MA2131-Jgg6 JPTS 98 001 SRC Review and Audit Requirements

~599824 Jg; ; 3p73 96 012 Design Features JPN 98 033 Response to written request for additional 07/23/98 information dated 6/1/98 Jgg5 Revision to proposed change regarding Design Features Jgg5 Response to written request for additional information dated 1/26/99 JPN 99 127 Affidavit to support proposed change 04/08/99 regarding Design Features MA4591 JPN 99 002 JPTS 99 001 LPRM Calibration 01/15/99 1

JPN 99 011 JPTS 99 002 Administrative Controls

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i FitzPatrick Improves Technical Specifications

("Beyond" CTS and "Beyond" ISTS)  :

i The following JAF ITS Specifications are those which are not in the CTS and are not a {

direct result of conversion to the ISTS. The specifications listed below include those  ;

identified in Attachment 5 of the ITS submittalletter (JPN-99-008, dated March 31, 1999). If an ITS specification is also in the CTS or, if a change proposed as part of the j conversion is consistent with NUREG 1433 or is addressed in a TSTF, it is not  ;

considered as "beyond beyond and is not listed below. l l

l 3.0.3 (JFD X2)- Be in MODE 3 was changed to allow a 9 hour1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Completion Time (other specifications also changed). This was approved for Duane Arnold. (Since CTS 3.0.C l does not include an intermediate time for being in Mode 3, the Mode 3 requirement was' )

added as M1 with the completion time of 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> to be in Mode 3. Tne Mi discussion i noted that the M1 change was consistent with 1433 except for the 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, which is due to thermal hydraulic stability Option I D.)

3.3.1.1 Reactor Protection System (RPS) Instrumentation Function 5 (L9)- reactor scram on MSIV closure. CTS is less than or equal to 10% and ITS is less than or equal to 14%.

3 3.5.1, L1 - CS and LPCI start timers values were changed and tolerances relaxed to allow the extension of CALIBRATION Frequency and LSFT from 6 to 24 months.

3.4.9 (L2)- RCS P/T Limits were changed to add a new alternate criteria to allow idle recirc pump (loop) start if the operating loop is >40% flow or if the idle loop is < 40% flow for less than or equal to 30 minutes.

3.5.1 (L7)- ECCS-Operating, reduced SAFER /GESTR LOCA flowrates replace existing CTS flowrates based on older SAFER /GESTR analyses. (Several editorial errors were just identified in the submittal: A. DOC L7 discusses change in LPCI and HPCI pump

! flows but CS is not mentioned; B. NUREG markup does not show any change to CS pump flow; and, C. Typed ITS shows CS flow reduced to 4100 gpm.)

3.5.2 (L5)- ECCS -Shutdown, SAFER /GESTR LOCA flowrates were changed as in ITS 3.5.1 for CS and RHR pumps.

3.6.1.9 (L5)- Residual Heat Removal (RHR) Containment Spray was changed to allow 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> to restore one subsystem when both subsystems are inoperable. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is consistent with NUREG-1434 for Containment Spray, NUREG-1433 for Suppression f Pool Spray and also with ITS 3.7.1- RHRSW, Condition D Completion Time.

3.6.2.3 (L4)- Residual Heat Removal (RHR) Suppression Pool Cooling was changed to allow 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore one subsystem when both subsystems are inoperable. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is consistent with ITS 3.7.1 - RHRSW, Condition D Completion Time, i

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3.8.1 (MS & JFD B 6) - AC Sources - Operating, Condition D for two reserve circuits inoperable wasj hanged to add new interim power reduction to less than or equal to 45% with a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> completion time. CTS allow 7 days to shutdown and ISTS allow 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to begin shutdown - both with no interim power reduction. (Since CTS allows 7 days with in interim power reduction the change are more restrictive rather the less ,

restrictive. JFD CLB6 notes that the NUREG 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time has been extended to 7 days consistent with CTS 3.9.B.2 and an additional requirement (Required Action D.2 ) has been added to require THERMAL POWER be reduced to

<45% RTP within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.)

3.8.4 (L2)- DC Sources - Operating changed battery terminal volts SR Frequency from 7 days to 31 days.

3.8.4 (L4)- DC Sources - Operating was changed to allow 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore one inoperable source. CTS allow 7 days and ISTS allaw 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. This change makes ITS

• 3.8.4 consistent with ITS 3.8.7. Distribution Systems - Operating, Condition A for one distribution subsystem inoperable.

3.8.6 (L1)- Battery Cell Parameters was changed Category A parameters (pilot cell SG, V and level) SR Frequency from 7 days to 31 days.

5.5 (L2)- VFTP (ITS 5.5.8) was changed to extend filter test Frequency to 24 months for some tests.

RETS Relocation l

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