ML20076C936: Difference between revisions
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6.9 A Routine Reoorts (Continued) 3.. | |||
Qtcunational Exoosure Tabulation Atabblationofthenumberofstation,utilityandotherpersonnel (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 supplements 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 body dose received from external sources shall be assigned to specific major work functions. | |||
4. | |||
Core Ooeratino Limits Reoort 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 cycie'. | |||
b) The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in NEDE-240ll.-P-A, " General Electric Standard Application for Reactor Fuel," (the approved version at the time the reload analyses are performed shall be identified in the CORE OPERATING LIMITS REPORT), | |||
and in NEDC-31852P, " Pilgrim Nuclear Power Station EAFER/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 OPERATING LIMITS REPORT), | |||
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 OPERATING LIMITS REPORT, including any mid-cycle r'evisions or supplements-thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector. | |||
6.9 B Deleted Amendment No. 122, 137 2178 9107250159 910717 ADOCK0500g3 DR | |||
_ _. _, ~ _ _ _.. _.. _ _,.}} | |||
Latest revision as of 07:50, 26 May 2025
| ML20076C936 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/17/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076C941 | List: |
| References | |
| NUDOCS 9107250159 | |
| Download: ML20076C936 (1) | |
Text
.. _
4 l
6.9 A Routine Reoorts (Continued) 3..
Qtcunational Exoosure Tabulation Atabblationofthenumberofstation,utilityandotherpersonnel (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 supplements 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 body dose received from external sources shall be assigned to specific major work functions.
4.
Core Ooeratino Limits Reoort 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 cycie'.
b) The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in NEDE-240ll.-P-A, " General Electric Standard Application for Reactor Fuel," (the approved version at the time the reload analyses are performed shall be identified in the CORE OPERATING LIMITS REPORT),
and in NEDC-31852P, " Pilgrim Nuclear Power Station EAFER/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 OPERATING LIMITS REPORT),
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 OPERATING LIMITS REPORT, including any mid-cycle r'evisions or supplements-thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
6.9 B Deleted Amendment No. 122, 137 2178 9107250159 910717 ADOCK0500g3 DR
_ _. _, ~ _ _ _.. _.. _ _,.