ML20246D155

Proposed Tech Specs,Clarifying Licensee 890612 Request for Amend to License NPF-62 Re Removal of Cycle Specific Parameter Limits for Tech Specs

ML20246D155
Person / Time
Site:	Clinton
Issue date:	08/17/1989
From:	ILLINOIS POWER CO.
To:
Shared Package
ML20246D139	List: ML20246D155 U-601499, Forwards Revised Tech Specs Clarifying Licensee 890612 Request for Amend to License NPF-62 Re Generic Ltr 88-16, Removal of Cycle Specific Parameter Limits for Tech Specs
References
NUDOCS 8908250272
Download: ML20246D155 (2)

Text

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U-601499 i- .

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Attachment 1 l

Page 1 of 2 ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)

The Semiannual Radioactive Effluent Release Reports shall include a li-st and description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period.

The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting. period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), pursuant to Specifications 6.13 and 6.14, respectively, as well as any major changes to liquid, gaseous, or Solid Radwaste Treatment Systems pursuant to Specification 6.15. It will also include a list-ing of new locations for dose calculations and/or environmental monitoring iden-tified by the land use census pursuant to Specification 3.12.2.

MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the main steam system safety /

H relief valves, shall be submitted on a monthly basis to the Document Control

{ Desk, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy

, to the Regional Administrator of the Regional Office of the NRC, no later than r+4 the 15th of each month following the calendar month covered by the report.

SPECIAL REPORTS-6.9.2 -Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

a.

Records and logs of unit operation covering time interval at each power level.

b.

Records.and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety.

c. All REPORTABLE EVENTS.

d.

Records of surveillance activities, inspections, and calibrations required by these Technical Specifications and the Fire Protection Program.

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ffK05000461 FDC CLINTON - UNIT 1 6-21

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 ; Attachment 1 Page 2 of 2 l Insert for Page 6-21 1

k, CORE OPERATING LIMITS REPORT 6.9.1.9 Core operating limits shall be established and documented in <-l Lthe CORE OPERATING LIMITS REPORT before each reload cycle or.any remaining part of a reload cycle. The analytical methods used to -i

~ determine the core operating limits shall be those previously reviewed and approved by the NRC in General Electric Standard Application for

_ Reactor Fuel (CESTAR), NEDE-24011-P-A-8, as amended (latest approved

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i version): and Maximum Extended Operating Domain and Feedwater Heater j Out-of-Service' Analysis for Clinton Power Station, NEDC-31546P, August I 1988. The core operating limits shallfbe determined so that all application 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. The CORE OPERATING LIMITS REPORT,-including any ,

-mid-cycle revisions or supplements thereto, for each reload cycle, shall  !

.be submitted upon issuance to.the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector. .

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