ML20217P143

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Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std
ML20217P143
Person / Time
Site: Prairie Island  
Issue date: 03/02/1998
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20217P134 List:
References
NUDOCS 9803100058
Download: ML20217P143 (8)
v • d • e


Text

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ATTACHMENT 1 i

SUPPLEMENT 6 to LICENSE AMENDMENT REQUEST DATED December 14,1995 Conformance of Administrative Controls Section 6 to the Guidance of Standard Technical Specifications Appendix A, Technical Specification Pages Marked Up Pages as proposed in this Supplement (shaded material to be added, strike-through material to be removed) 1 TS.6,0-13 (from December 29,1997 supplement)

TS.6.0-14 (from December 29,1997 supplement) i i

9903100058 980302 PDR ADOCK 050002824-

TS.6.0-13 l

I D. Monthly Operatino Reports Routine reports of operating statistics and shutdown experiences IHsilidijiiid5EsissHtistif6HI[6f fsll!cha11ssgss^#BTthi~)Yes'ihrizef powet l

operatedikyliefjjalpesiorjressurizepinafeMvs1ves{ shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

E. Core Operatino Limits Report (COLR)

1. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

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a. Heat Flux Hot Channel Factor Limit (Fg ), 14uclear Enthalpy RTP Rise "Iot Channel Factor Limit (FAg ), PFDH, K(Z) and V(Z)

(Specifications 3.10.B.1, 3.10.B.2 and 3.10 B.3)

b. Axial Flux Difference Limits and Target Band (Specifications 3.10.B.4 through 3.10.B.9)
c. Shutdown and '?ontrol Bank Insertion Limits (Specification 3.10.D)
d. Reactor Coolant System Flow Limit (Specification 3.10.J)
2. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

NSPNAD-8101-A, " Qualification of Reactor Physics Methods for Application to PI Units" (latest approved version)

NSPNAD-8102-A, " Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units" (latest approved version)

WCAP-9272-P-A, " Westinghouse Reload Safety Evaluation Methodology", July, 1985 WCAP-10054-P-A, " Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code", August, 1985 WCAP-10924-P-A, " Westinghouse Large-Break LOCA Best-Estimate Methodology", December, 1988 1

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TS.6.0-14 j

- 6 I E. Core Operatino Limits Reoort (COLF. tecntinued.

WCAP-10924-P-A, Volume 1, Addendum 4, " Westinghouse Large Break LOCA Best Estimate Methodology", August, 1990 l

XN-NF-77-57 (A), XN-NF-77-57, Supplement 1 (A), " Exxon Nuclear I Power Distribution Control for Pressurized Water Reactors Phase II", May, 1981 WCAP-13677, "10 CFR 50.46 Evaluation Model Report: W-COBRA / TRAC 2-Loop Upper Plenum Injection Model Update to Support ZIRLOn4 Cladding Options", April 1993 (approved by NRC SE dated November 26, 1993).

NSPNAD-93003-A, " Transient Power Distribution Methodology",

(latest approved version)

3. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, transient analysis limita and accident analysis limits) of the safety analysis are met.
4. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

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r 4 9 ATTACHMENT 2 SUPPLEMENT 6 to LICENSE AMENDMENT REQUEST DATED December 14,1995 l Conformance of Administrative Controls Section 6 to the Guidance of Standard Technical Soecifications Appendix A, Technical Specification Pages Revised Pages as proposed in this Supplement (Changes from current Technical Specifications sidelined)

TS.6.0-13 TS.6.0-14 l

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I TS.6.0-13 I

l 4

D. Monthlv Ooeratino Reports Routine reports of operating statistics and shutdown experience,

, including documentation of all challenges to the pressurizer power operated relief valves or pressurizer safety valves, shall be submitted on a monthly basis no later than the 15th of each month following the l

l calendar month covered by the report.

E. Core Operatino Limits Report (COLR)

1. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, l and shall be documented in the COLR for the following:

RW

a. Heat Flux Hot Channel Factor Limit (Fg ), Nuclear Enthalpy RTP Rise Hot Channel Factor Limit (Fag ), PFDH, K(Z) and V(Z)

(Specifications 3.10.B.1, 3.10.B.2 and 3.10.B.3)

b. Axial Flux Difference Limits and Target Band (Specifications 3.10.B.4 through 3.10.B.9)
c. Shutdown and Control Bank Insertion Limits (Specification 3.10.D)
d. Reactor Coolant System Flow Limit (Specification 3.10.J)
2. The analytical methods used to determine the core operating l limits shall be those previously reviewed and approved by the

! NRC, specifically those described in the following documents: )

NSPNAD-8101-A, " Qualification of Reactor Physics Methods for 1 l

Application to PI Units" (latest approved version)

NSPNAD-8102-A, " Prairie Island Nuclear Power Plant Reload l Safety Evaluation Methods for Application to PI Units" (latest approved version) l WCAP-9272-P-A, " Westinghouse Reload Safety Evaluation i Methodology", July, 1985 WCAP-10054-P-A, " Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code", August, 1985 WCAP-10924-P-A, " Westinghouse Large-Break LOCA Best-Estimate Methodology", December, 1988 l

l

e i

TS.6.0-14 l E. E2.re Operatino Limits Reoort (COLR) (continued)

WCAP-10924-P-A, Volume 1, Addendum 4, " Westinghouse Large Break LOCA Best Estimate Methodology", August, 1990 XN-NF-77-57 (.A ) , XN-NF-77-57, Supplement 1 (A), " Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II", May, 1981 WCAP-13677, "10 CFR 50.46 Evaluation Model Report: W-COBRA / TRAC 2-Loop Upper Plenum Injection Model Update to Support ZIRLOy L

Cladding Options", April 1993 (approved by NRC SE dated

November 26, 1993).

l NSPNAD-93003-A, " Transient Power Distribution Methodology",

I (latest approved version)

3. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core l thermal-hydraulic limits, ECCS limits, nuclear limits such as shutlown margin, transient analysis limits and accident analysis limits) of the safety analysis are met.
4. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

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r ATTACHMENT 3 SUPPLEMENT 6 LICENSE AMENDMENT REQUEST DAYED December 14,1995 Conformance of Administrative Controls Section 6 to the Guidance of Standard Technical Soccifications Final License Amendment Pages Note: All of the current Technical Specification Chapter 6 pages were deleted, including Table 6.1-1, by the original submittal and replaced with pages TS.6.0-1 through TS.6.0-15.

< Page Number Source Document Page Number Source Document l

l TS-ii Original submittal TS.6.0-2 Supplement (11/25/96)

TS-v Supplement (11/25/96) TS.6.0-3 Supplement 3 TS-viii Supplement 4 TS.6.0-4 Supplement (11/25/96)

TS-ix Supplement 4 TS.6.0-5 Supplement 2 TS-x Supplement 4 TS.6.0-6 Original submittal TS-xi deleted - Supplement 3 TS.6.0-7 Supplement (11/25/96) l TS-xii deleted - Supplement 3 TS.6,0-8 Supplement (11/25/96)

TS-xiii deleted - Original submittal TS.6.0-9 Supplement 5 TS.3.1-10 Original submittal TS.6.0-10 Supplement 4 TS.3.1-11 deleted - Original submittal TS.6.0-11 Supplement 4 l

Table Supplement 4 TS.6.0-12 Supplement 4 l TS.4.1-28 (Page 1 of 2) TS.6,0-13 Supplement 6 TS.4.4-3 Supplement 4 TS.6.0-14 Supplement 6 TS.4.6-1 Original submittal TS.6.0-15 Supplement 4 f TS.S.1-1 Original submittal TS.6.0-16 Supplement 4 ,

l TS.S.1-2 Original submittal B.3.1-9 deleted - Original submittal TS.6.0-1 Original submittal B.4.4-3 Supplemerit 4

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., V ATTACHMENT 4 SUPPLEMENT 6

\ to l LICENSE AMENDMENT REQUEST DATED December 14,1995 l Conformance of Administrative Controls Section 6 to the Guidance of Standard Technical Soecifications i Status of Relocated Requirements

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3.1.E - Maximum ReactorCoolant Oxygen, Currently in plant procedures, will be - I l

l Chloride and Fluoride Concentration relocated to USAR(TRM) by Jan 1,2001 l l

4.4.D RHR System Complete - part of Primary Coolant Sources Outside Containment Program l

l 4.6.A.1.c Diesel Fuel Oil Testing incorporate in Diesel Fuel Oil Testing l Program upon implementation of Chapter- l 6 LAR (90 days afterissuance) l l 5.1 Flood shutdown requirements Currently in plant procedures, will be relocated to USAR(TRM) by Jan 1,2001 ,

6.2 SAC, OC requirements Complete -incorporated into OQAP 6.3 SpecialInspections and Audits Complete - contained in OQAP and Fire l

Protection Program -

l 6.4 Safety Limit Violation Complete - incorporated in TS.2.2 by Amendment 123/116

6.5.C Maintenance and Test Procedure Complete -incorporated into OQAP L requirements l
6.5.A.5 Emergency Plan procedures Complete -incoporated into OQAP 6.5.B.3 Emergency Plan requirements Complete - incorporated into Emergency Plan 6.5.F Security Plan procedure requirements Complete - part of Security Plan and relocated to OQAP 6.5.G Temporary Changes to procedures Complete -incorporated into OQAP 6.6 Plant Operating Records Complete -incorporated into OQAP

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