ML20067C978

Proposed Tech Specs Re Analytical Methods Used to Determine Core Operating Limits

ML20067C978
Person / Time
Site:	Pilgrim
Issue date:	02/06/1991
From:	BOSTON EDISON CO.
To:
Shared Package
ML20067C976	List: BECO-91-013, Application for Amend to License DPR-35,changing Tech Specs to Establish Revised Basis for Safety Analyses Based on Results of GE Safer/Gestr LOCA Analysis Methodology ML20067C978
References
NUDOCS 9102120276
Download: ML20067C978 (4)

Text

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1 ATTACHMENT B REPLACEMENT TECHNICAL SPECIFICATION PAGE (One Page) 9 p0 p$!?O276910206HDOCK O'5000293 PDR

.c 6.9.A REVtine Reoorts (Continued) c

-3. Occupational Exopiure Tabulation A tabulation of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and-their associated man-rem exposure according to work and job ~

functions, e.g. reactor operations and surveillance inservice inspection, routine maintenance, special maintenance (including a description), waste processing, and refueling shall be submitted on an annual basis. This tabulation suppiements the requirements of 20.407 of 10 CFR 20. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted.for. -In the aggregate, at least 80% of the total whole oody dose received from external

! sources shall be assigned to specific major work functions.

l 4. Core Ooerating_ Limits RpppLt 1

a) Core operating limits shall be established and documented in the CORE-OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle.

b) The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in E' NEDE-24011-P-A, " General Electric Standard Application for Reactor

'Fual," (the approved version at the time the reload analyses are performed shall be identifled in the CORE OPERATING LIMITS REPORT),

and in NEDC-31852P, " Pilgrim Nuclear Power Station SAFER /GESTR-LOCA Loss of Coolant Accident Analysis", dated September,1990 (the approved version at the time'the reload analyses are performed shall be identified in the CORE OPEPATING LIMITS REPORT).

c) The core operating Ilmits shall be determined so 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) are met.

d) The CORE OPiRATING LIMITS REPORT, including any mid-cycle revisions nr supplements thereto, shall be provided upon issuance, for each .

. reload cycle, to the NRC Document Control Desk with copie'. to the

-Regional Administrator and Resident Inspector.

6.9 B Deleted i

(-

Amendment No. 133 217a 1

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ATTACHMENT C 1 MARK-UP TECHNICAL SPEClilCi? ION PAGE (One Page) s

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i i

6.9.A Peutine IgyA (Continued)

3. Oce"entional Excesure Tabulation A tabulation of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr  !

and their aturlaNd man.. rem exposure according to work and job '

4 functions, e.g. reactc operations and surveillance inservice inspection, routine maintenance, special maintenance (including a description), waste processing, and refueling shall be submitted on an annual basis. This tabulation supplements the requirements of 20.407 of 10 CFR 20. The dose assignment to various duty functions

- 1 may be estimates based on pocket dosimeter, TLD, or film badge measun.aent s. Small exposures totalling less than 207 of the individual total dose need not be accounted fer. In the aggregate, i at least 80% of the total whole body dose received from external <

sources shall be assigned to specific major work functions.

4. Core Ooeratina limits Recort a) Core oDeratinii limits shall' be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle, b) The analytical methods used to determine the core operating limits thall br those previously reviewed and approved by the NRC in NEDE-240*1-P-A, " General Electric Standard Application for Reactor fuel," (tne s,cproved version at the time the reload analyses are perfor shall be identified in the CORE OPERATING LIMITS REPORT) and i NEDO- T696 " Loss of coolant Anal sis Redo *t for Pilgrim ear Power Station," dated' August 197{4.I(the approved v at me time Ine reload analyses are perforseT shall be identified in the

, CORE OPERATING LIMITS REPORT).

i c)- The core operating limits shall be determined so 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) are met, d) The CORE OPERATI d .tHITS REPORT, including any mid-cycle revisions

" or supplements thereto, shall be provided upon issuance, for each roload cycle to'the NRC Document Control Desk with copies to the i

RegionalAdministratorandResidentInspector.

6.9.B Deleted '

/vs p C - 3/ 6 S2 P, " .ht!" U"(9/E SGL L .sG a nrn TC Cyr/i'N SiA/#~6A'/SGT72"4 0CA /- OH eG [acusur lccmecT As>Atwit; pew ranvr'a ece 19 90 Amendment No. 217a 133, l '

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