ML20247H342

Proposed Tech Specs Removing Certain Cycle 7 Parameter Limits,Per Generic Ltr 88-16

ML20247H342
Person / Time
Site:	Three Mile Island
Issue date:	05/18/1989
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20247H339	List: ML20247H333 ML20247H342 ML20247N591
References
GL-88-16, NUDOCS 8905310213
Download: ML20247H342 (4)

Text

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LIST OF FfGURES Figure Title 3.5-2K DELETED 3.5-2L DELETED 3.5-2M LOCA Limited Maximum Allowable Linear Heat Rate 3.5-1 Incore Instrumentation Specification Axial Imbalance Indication, TMI-1 3.5-2 Incore Instrumentation Specification Radial Flux Tilt Indication, TMI-1 3.5-3 Incore Instrumentation Specification 3.11-1 Transfer Path to and from Cask Loading Pit 4.17-1 Snubber Functional Test - Sample Plan 2 5-1 Extended Plot Plan TMI 5-2 Site Topography 5 Mile Radius 5-3 Locations of Gaseous Effluent Release Points and Liquid Effluent Outfalls griBa!!!8188$y P

viii Amendment Nos. 72, 77, 126, 139, 142

1.I9 PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a-confinement to maintain temperature, pressure, humidity, concentration or other operating. conditions in such a manner that replacement air or gas is required to purify the confinement.

1.20 VENTING VENTING is the controlled process of discharging air as gas from a confinement to maintain temperature, pressure,. humidity, concentration or other operating conditions in such a manner that replacement air or gas is not provided. Vent used in system name does not imply a VENTING process.

1.21 REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

1.22 MEMBER (S) 0F THE PUBLIC MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category dess not include employees of the GPU System, GPU contractors or vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

1.23 SUBSTANTIVE CHANGES SUBSTANTIVE CHANGES are those which affect the activities associated j

with a document or the document's meaning or intent. Examples of l

non-substantive changes are: (1) correcting spelling; (2) adding (but not deleting) sign-off spaces; (3) blocking in notes, cautions, etc.;

(4) changes in corporate and personnel titles which do not reassign responsibilities and which are not referenced in the Appendix A Technical Specifications; and (5) changes in nomenclature or editorial changes which clearly do not change function, meaning or intent.

1.24 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT is a TMI-1 specific document that provides core operating limits for the current operating reload cycl e. These cyc-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.5. Plant operation within these operating limits is addressed in individual specifications.

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l- 1-7 Amendment No. 72, 137, 141 i

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e. If an acceptable axial power imbalance is not achieved within four hours, reactor power shall be reduced until imbalance limits are met.

f. Axial power imbalance shall be monitored on a minimum frequency of once every two hours during power operation above 40 percent of rated power.

3.5.2.8 A power map shall be taken at intervals not to exceed 30 l l effective full power days using the incore instrumentation detection system to verify the power distribution is within the limits shown in Figure 3.5-2M.

Bases The axial power imbalance, quadrant power tilt, and control rod position limits are based on LOCA analyses which have defined the maximum linear heat rate (see Figure 3.5-2M). These limits are developed in a manner that ensures the initial condition LOCA maximum j linear heat rate will not cause the maximum clad temperature to exceed the Final Acceptance Criteria (10 CFR 50 Appendix K).

Operation outside of any one limit alone does not necessarily constitute a situation that would cause the Final Acceptance Criteria to be exceeded should a LOCA occur. Each limit represents the 1 boundary of operation that will preserve the Final Acceptance Criteria even if all three limits are at their maximum allowable values simultaneously. The effects of the gray APSRs are included in ,

the limit development. Additional conservatism included in the limit j development is introduced by application of: l

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a. Nuclear uncertainty factors 1 l

b. Thermal calibration uncertainty

c. Fuel densification effects

d. Hot rod manufacturing tolerance factors

e. Postulated fuel rod bow effects

f. Peaking limits based on initial condition for Loss of Coolant Flow transients. I The incore instrumentation system uncertainties used to develop the axial power imbalance and quadrant tilt limits accounted for various combinations of invalid SPND signals. If the number of valid SPND l signals falls below that used in the uncertainty analysis, then '

another system shall be used for monitoring axial power imbalance and/or quadrant tilt.

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3-35a l

Amendment No. 17, 29, 38, 39, 50, 120, 126, 142 i

6.9.5.2 The analytical methods used to determine the core operating limits addressed by the individual Technical Specifications shall be those previously reviewed and approved by the NRC for use at TMI-1, specifically:

(1) BAW-10122A Rev. 1, " Normal Operating Controls,"

May 1984.

6.9.5.3 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 / accident analysis limits) of the safety analysis are met.

6.9.5.4 The ' CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance for each reload cycle to the NRC Document Cont'ol Desk with copies to the Regional Administrator and Resident Inspector.

6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a. Records of normal station operation including power levels and periods of operation at each power level.

b. Records of principal maintenance activities, including inspection, repairs, substitution, or replacement of principal items of equipment related to nuclear safety.

c. All REPORTABLE EVENTS.

d. Records of periodic checks, tests and calibrations.

e. Records of reactor physics tests and other special tests related to nuclear safety.

f. Changes to procedures required by Specification 6.8.1.

g. Records of solid radioactive shipments. l l

l 6-19a Amendment No. 72, 77, 129, 137, 141 i

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