ML20059L358

Proposed Tech Specs Revising Section 6.7.A.6.b to Incorporate Ref to Revised Methodologies Described in WCAP-10924-P

ML20059L358
Person / Time
Site:	Prairie Island
Issue date:	09/13/1990
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20059L347	List: ML20059L343 ML20059L356 ML20059L358
References
NUDOCS 9009260262
Download: ML20059L358 (8)

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Exhibit B

>: I Prairie Island Nuclear Generating Plant l 1

License imendment Roquest Dated September 13, 1990 Proposed Changes Marked Up on Existing Technical Specification Pages j Exhibit B consists of the existing Technical Specification page with the proposed changes written on that page. The existing page affected by this License Amendment Request is listed below-1 D

TS 6.7 4 ]

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( .7. A.5. Annual S-= ries of Meteorolorical Data An annual summary of meteorological data shall be submitted for the previous calendar year in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability at the request of the Commission.

6.7.A.6. Core Ocaratina Limits Reeort

a. Core operating limits shall be established and documented in the CeRE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1. Heat Flux Hot Channel. Factor Limit (FRPT),q Nuclear Enthalpy Rise Hot Channel Factor Limit (F (Specifications 3.10.B.1, 3.10.H ), and B.2 PFDH, K(Z) and V(Z) 3.10.B.3)

2. Axial Flux Difference Limits and Target Band (Specifications 3.10 B.4 through 3.10.B.9)

3. Shutdown and Control Bank Insertion Limits (Specification 3.10.D)

4. Reactor Coolant System Flow Limit (Specification 3.10.J)

b. 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 Powet Plant Reload Safety Evaluation Met. hods for Application to PI Units" (latest approved version)

WCAP 9272 P A, " Westinghouse Reload Safety Evaluation Methodology", July,1985 l

. VCAP 10924 P.A Volume 1, WCAP 10054-P A, " Westinghouse Small Break ECCS Evaluation Model J Addendum 4. "Vestinghouse Using the NOTRUMP Code", August, 1985 f Large Break IDCA Best EOtimate Methodology *, WCAP 10924 P A, " Westinghouse Large Break LOC /. Best Estimate October 1990 Methodology", December,1988 XN-NF-77 57 (A), XN NF 77 57, Supplenient 1 (A), " Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II", May, 1981

c. 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, and transient and accident analysis limits) of the safety analysis are met. ,

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Exhibit C .)

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License' Amendment Request Dated September 13, 1990 -: !

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r REVISED TECHNICAL SPECIFICATIONS PAGES l

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' Exhibit C consists'of revised pages for'the Prairie' Island Nuclear Generating-E

-j Plant Technical Specifications with the proposed changes incorporated as J

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TS ix TS.6'.7 4 ,

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TS ix TABLE OF CONTENTS (Continued)

TS SECTION TITLE PAGE 6.7, Reporting Requirements TS.6.7 1 A. Routine Reports TS.6.7 1 1.~ Annual Report _ TS.6.7 1

a. Occupational Exposure Report . .TS.6.7 1

b. Report of Safety and Relief Valve .

Failures and Challenges TS.6.7 1

c. Primary Coolant Iodine Spike Report. TS 6.7 1

2. Startup Report TS.6.7 2

3. Monthly Operating Report TS.6.'7 2

4. Semiannual Radioactive Effluent Release Report TS.6.7 3 S.LAnnual Summaries of Meteorological Data TS.6.7-4

6. Core Operating Limits Report TS 6.7 4 B. Reportable Events TS.6.7 5

c. Environmental Reports ~ TS.6.7 6-1.' Annual Radiation Environmental Monitoring.

Reports _ .

TS.6.7 6

2. Environmental Special Reports _ TS.6.7 6

3. Other. Environmental Reports TS.6.7 7' (non radiological, non-aquatic)

D.:Special' Reports TS.6.7 7

TS.6.7 4 6.7. A.5. Anraal Summaries of Meteoro1orical Data An annual summary of meteorological data shall be submitted for the previous calendar year in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability at the request of the Commission.

6.7.A,6. Core Operatine Limits Report

a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT cefore each reload cycle or any remaining part of a reload cycle for the following:

1. Heat Flux Hot Channel Factor Limit (FRPT),q Nuclear Enthalpy Rise Hot Channel Factor Limit (F n ), PFDH, K(Z) and V(Z)

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

2. Axial Flux Difference Limits tad Target Band (Specifications 3.10.B.4 through 5.10.B.9)

3. Shutdown and Control Bank Insertion Limits (Specification 3.10.D)

4. Reactor Coolant System Flow Limit (Specification 3.10.J)

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NPO, specifically those described in the following documents:

NSPNAD 8101 A, " Qualification of Reactor Physics Methods for i Applic.ation 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 Mnthodology", December, 1988 WCAP 10924 P A, Volume 1, Addendum 4. "Westinghnuse Large Break LOCA Best Estimate Methodology", October,1990 l;

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TS.6.7 5 l 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

c. The core operating limits shall be determined such that all l i

applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, ECCS timits, nuclea limits such as shutdown margin, and transient and accident a alysis limits) of l the safety analysis are met. j i

d. The CORE OPERATINC LIMITS REPORT, including at.y mid cycle. revisions- l or supplements thereto, shall be supplied upon issuance, for each  ;

reload cycle, to the NRC Document Control Desk with copies to the  !

Regional Administrator and Resident Inspector, ,

B. REPORTABLE EVENTS The following actions shall be takeri for REPORTABLE EVENTS:

a. The Commission shall be notified by a report submitted pursuant 3 to the requiremeatn of Section 50.73 to 10 CFR Part 50, and '

b. Each REPORTABLE EVENT shall be reviewed by the Operations Committee and the results'of this review shall be submitted to the Safety Audit Committee and the Vice President Nuclear Generation.

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TS 6.7 6 L

C. Environmertal Reoorts The reports listed below shall be submitted to the Administrator of the appropriate Regional NRC Office or his designate:

1, Annual Radiation Environmental Monitorine Reoort (a) Annual Radiation Environmental Monitoring Reports covering the operation of the program during the previous calendar year shall be submitted prior to May 1 of each year.

(b) The Annual Radiation Environmental Monitoring Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 4.10 B.1, If harmful effects or evidence of irreversible damage are detected by.the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem. -

(c) The Annual Radiation Environmental Monitoring Reports shall include summarized and tabulated results in the format of Regulatory cuide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be aubmitted as soon as possible in a supplementary report.

(d) The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensees participation in the Interlaboratory Comparison Program, required by Specification 4.10.C.1,

2. Environmental Special Reports (a) When radioactivity levels in samples exceed limits specified in Table 4.10 3, an Environmental Special Report shall be subinitted within 30 days from the end of the affected calendar quarter. For certain cases involving long analysis time, determination of quarterly averages may extend beyond the 30 day period. In these cases the potential for exceeding the quarterly limits will be reported within the 30 day period to be followed by the Environmental Special Report as soon as practicable.

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3. Other Environmental Reports (non radiolorical. non anuatic)

Written reports for the following items shall be submitted to l the appropriate NRC Regional Administrator:  !

a. Environmental events that indicate or could result in a l significant environmental impact casually related to plant  :

operation. The following are examples: excessive bird l impaction; onsite plant or animal disease outbreaks; unusual mortality of any spec!.es protected by the ,

Endangered Species Act of 1973; or increase in nuisance organisms or. conditions. This report shall be submitted I within 30 days of the event and shall (a) describe, analyze, and evaluate the event, including extent and magnitude of1 the impact and plant operating characteristics, (b) describe the probable cause of the event, (c) indicate the >

action caken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar ,

components or systems, and (e) indicate the agencies notified and their preliminary responses. -

b. Proposed changes, test or experiments which may result in a significant increase in any adverse environmental impact which was not previously reviewed or evaluated in the Final Environmental Statement or su; elements thereto. This  :

report shall include an evaluattus of the environmental -

impact of the proposed activity and shall be submitted 30 days prior to implementing the proposed change, test or experiment.

D. Soccial Reports Unless otherwise indicated, special reports required by t' e Technical Specifications shall be submitted to the appropriate NRC Aegional Administrator within the time period specified for each report. +

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