ML20065M942
| ML20065M942 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/03/1990 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20065M940 | List: |
| References | |
| NUDOCS 9012110261 | |
| Download: ML20065M942 (2) | |
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l 1.0 DEFINITIONS l
The succeeding frequently used terms are explicitly defined so that a i
uniform interpretation of the.t :ecifications may be achieved.
A.' Safety Limit - The safety limits are limits'below which the reasonable maintenance of the cladding and primary systems are assured.
1 Exceeding such a limit is cause for unit shutdown and review by.the Nuclear Regulatory Commission before resumption of unit operation.
Operation beyond such a limit may not in itself result in serious consequences but it indicates an operational. deficiency subject to regulatory review.
B. Limitino Safety System settina (LSSS) - The limiting safety system settings are-settings on instrumentation which initiate the automatic protective action at a level.such that the safety limits will not'be exceeded. The region between the safety limit and these settings.
i represent margin with normal operation ly ng below these settings.
The margin has been established so that w th proper operation of the' r
instrumentation the safety limits will never be exceeded..
C. Limitina Conditions for Ooeration (LCO) - The limiting conditions for; e
operation specify the minimum acceptable levels of system performance necessary to assure safe startup and operation of the facility.
When these conditions are met, the plant can be operated safely and abnormal situations can be' safely controlled.
D.. CORE OPERATING LIMITS REPORT i
The CORE OPERATING LIMITS ~ REPORT is a reload-cycle specific document, 1
its supplements and revisions, that provides core operating. limits for the current operating reload cycle.
These cycle specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.A 4.
Plaa+ operation within these operating limits is addressed. in: individual._, 'ifications.
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' B.9.A Routine Reports (Continued) 3.
Occupational Exoosure Tabulation 2
- A tabulation of the number of station', utility and other personnel (incluaing contractors) receiving exposures greater than 100 mrem /yr j
and their associated man-rem exposure according to work and job-functions, e.g. reactor operations and surveillance' inservice -
t inspection.-routine maintenance, special maintenance (including a l
description), waste processing, and refueling shall be. submitted on an annual basis. This tabulation supplementsLthe requirements of r
20.407 of 10 CFR 20.
The dose assignment to various duty functions i
may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling iess.than 20% of the-i individual total dose need not be accounted for.
IntheLaggregate,-
i at least 80% of the total whole body dose received-from' external:
i sources shall be assigned to specific major work functions.
4.
Core Ooeratina Limits Report t-a) Core operating limits shall be established and documented in the CORE I
OPERATING LIMITS REPORT before each reload cycle or-any. remaining i
part of a reload cycle.
i b) The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel," (the approved version at the time the reload analyses are e
performed shall be identified in the CORE OPERATING LIMITS REPORT) and in NED0-21596, " Loss of Coolant Analysis Report for Pilgrim Nuclear Power Station," dated August 1977, (the approved version at the time the reload analyses are performed shall be identified.in the CORE OPERATING LIMITS REPORT).
j 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 r
transient and accident analysis limits) are met.-
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d) The CORE OPERATING LIMITS REPORT, including.any mid-cycle revisions.
1 or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control-Desk'with copies'to the f
Regional Administrator and Resident Inspector.
f 6.9.B Deleted L
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" Amendment No. 88',
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