ML20116C376

Proposed Tech Specs,Reflecting Deletion of Figure 3.5-2M

ML20116C376
Person / Time
Site:	Three Mile Island
Issue date:	10/29/1992
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20116C368	List: ML20116C367 ML20116C372 ML20116C376
References
NUDOCS 9211030345
Download: ML20116C376 (5)

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LIST Of fit 15 f_Lqurs Tit 1e 3.5-2K thru DELETED 3.5-2L 3.5-2M DELETED 3.5-1 Incore Instrumentation Specification Axial imbalance Indication, IMI-l 3.5-2 incore Instrumentation Specification Radial flux Tilt Indication, 1MI-l 3.5-3 Incore Instrumentation Specification 3.11-1 Transfer Path to and from Cask Loading Pit I

4.17-1 Snubber functional Test - Sample Plan 2 5-1 Extended Plot Plan TH1 5-2 Site Topography 5 Mile Radius 5-3 Locations of Gaseous Effluent Release Points and Liquid Ef fluent Outfalls 1

viii-Amendment hos 12. 11, m "9,142, 349, 35D,156,104

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e. If an ecceptoble extal power imbolence is not achieved tsithin 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 effective full power days using the incore instrumentation detection system to verify the power distribution is within the limits shown in the CORE OPERATING LIMITS REPORT.

Enti lhe axial power imbalance, qurJrant power tilt, and control rod position limits are based on LOCA analyses which have defined the maximum linear heat rate. These lim'ts are developed in a manner that ensures the initial condition LOCA maximum linear heat rate will not cause the maximum clad temperature to exceed 10 CFR 50 Appendix K. Operation outside of any one limit alone does not necessarily constitute a situation thct would cause the Appendix K Criteria to be exceeded should a LOCA occur. Each limit represents the boundary of operation that will preserve the Acceptance Criteria even if all three limits are at their maximum allowable values ,

simultaneously. The effects of the APSRs are included in the limit l development. Additional conservatism included in the limit development is I introduced by application of:

a. Nuclear uncertainty factors

b. Thermal calibration uncertainty

c. Fuel densification effects i

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.

The incore 2nstrumentation system uncertainties used to develop the axial power imbalace and quadrant tilt limits accounted for various combinations

of invalid Self Powered-Neutron Detector (SPND) signals, if the-number of l valid SPND signals falls below that used in the uncertainty analysis, then i another system shall be used for monitoring axial power imbalance and/or quadrant-tilt.

3-35a Amendment No. J/, Jp, pp, Jp, Ep, ))p, )#, AM, 150, 157 i

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FIGURE DELETED AND INCORPORATED INTO THE CORF OPERATING LIMITS REPORT.

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6.9.5.2 The analytical methods used to oetermine the core operating limits addressed by the individual Technical S)ecifications shall be those previously reviewed and approved )y the NRC for use at THI-1, specifically:

(1) BAW-10122A Rev.1, " Normal Operating Controls," May 1984.

(2) BAW-10ll6-A, " Assembly Calculations and Fitted Nuclear Data,"

May 1977.

(3) BAW-10ll7P-A, " Babcock & Wilcox Version of PDQ User's Manual," January 1977.

(4) BAW-10llBA, " Core Calculational Techniques and Procedures,"

December 1979.

(5) BAW-10124A, " FLAME 3 - A Three-Dimensional Nodal Code for Calculating Core Reactivity and Power Distributions," August 1976.

(6) BAW-10125A, ' Verification of Three-Dimensional FLAME Code,"

August 1976.

(7) BAW-10152A, "NDODLE - A Multi-Dimensional Two-Group Reactor ,

Simulator," June 1985.

(8) BAW-10119. " Power Peaking Nuclear Reliability Factors," June 1977.

(9) BAW-10103, Rev. 3 "ECCS Analysis of B&W's 177-FA Lowered Loop NSS," July 1977.

(10) BAW-1915P-A, " Bounding Antlytical Assessment of NUREG-0630 Models on LOCA kw/ft Limits With Use of FLECSET," May 1986.

(11) BAW-10104P-A, Rev. 5, B&W ECCS Evaluation Model," November 1988.

(12) BAW-10162P-A, " TACO-3 fuel Pin Thermal Analysis Computer Code," November 1989.

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 provide.) u)on issuance for each reload cycle to the NRC Document Control Des ( 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 o cration including power levels and periods of operation at eac1 power level.

b. Records _ of 3rincipal maintenance artivities, including inspection, repairs, suastitution, or replacer at of principal items cf equipment related to nuclear safeb ,

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.

6-19a Amendment No. 72, 77, 123, 137, JA1, 149, 150

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f. Changes to procedures required by Specification 6.8.1.

g. Records of solid radioactive shipments.

h. Test results, in units of microcuries, for leak tests performed on licensed sealed sources.

1. Results of annual physical inventory verifying accountability of licensed sources on record, J. Control Room Log Book.

k. Shift foreman log Book.

6.10.2 The following records shall be retained for the duration of Operating License DPR-50 unless otherwise specified in 6.10.1 above.

a. Records and drawing changes reflecting facility design modifications made to systems and equipment described in the final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Routine unit radiation surveys and monitoring records.

d. Records of radiation exposure history and radiation exposure status of personnel, including all contractors and unit visitors who enter radioactive material areas.

e. Records of radioactive liquid and gaseous wastes released to the environment, and records of environmental monitoring surveys,

f. Records of transient or operational cycles for those facility components which affect nuclear safety for a limited number of transients r* cycles as defined in the Final Safety Analysis _

Report.

g. Records of training and qualification for current members of the unit staff,

h. Records of in-service inspections performtd pursuhnt to these Technical Specifications,

i. Records of Quality Asturance activities required by the Operational Quality Assurance Plan.

J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of reviews by the Independent Onsite Safety Review Group.

1. Records of analyses required by the radiological environmental monitoring program.

6-20 Amendment No. II, 64, 72, 77, 129, 141

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