ML20128L001
| ML20128L001 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/11/1993 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20128L004 | List: |
| References | |
| DPR-50-A-168 NUDOCS 9302190071 | |
| Download: ML20128L001 (8) | |
Text
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gF UNITED STATES 3'
'o#'n NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D C. 205$5
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METROPOLITAN EDISON COMPANY dG1EY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC C0KfANY GPU NUCLEAR CORPORATION QOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION. VNiT NO. 1 AMEN 0 MENT T0 FACILITY OPERATING LICENSE Amendment No.168 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by GPU Nuclear Corporation, et al.
(the licensee), dated August 9, 199' and 0%tober 29, 1992, comply with the standards and requirements 9.he Atoni;c Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and-E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9302190071 930211 PDR ADOCK 05000289 p
4 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No.
DPR-50 is hereby amended to read as follows:
(2) 11qhnical Specifications The rechnical Specifications contained in Appendix A, as revised through Amendment No.168, are hereby incorporated >in the license. GPU Nuclear Corporation shall operate thes
~
facility in accordance with the Technical Specifications'. /
3.
This license amendment is effective as of its date of issdance, to be implemented within 60 days of is;uance.
FOR THE NUCLEAR REGULA10RY COMMISSION 5~'
, Jol
- f. Stolz,7Direcip
/ Pr ject Directorate 1 b(1visionofReactor rojects - I/II Office of Nuclear R,eactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 11, 1993
ATTACHMENT TO LICENSE AMENDMENT N0.16_8 2
FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
flgmqv_c Insert viii vili 3-20 3-20 3-35a 3-35a 3-36b (Figure 3.5-2M) 3-36b (" DELETED" Figure 3.5-2M) 6-19a 6-19a 6-20 6-20 s
a i~
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ql (15I_.0F FIGURES Fioure Title i
3.5-2K thru.
DELETED 3.5-2L 3.5-2H DELETED s
y 3.5-1 Incore Instrumentation Specification Axial Imbalance Indication, THI-l 3.5-2 Incore Instrumentation Specification Radial Flux Tilt Indication, THI-1 3.5-3 Incore Instrumes:tation 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 THI 5-2 Site Topocraphy 5 Mile Radius 5-3 Locations of Gaseous Effluent Release Points and Liquid Effluent Outfalls viii Amendment Nos. 12. 17. 2 " "9,A42: AAS,150,155, 164,168
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a The quantity of boric acid in storage from either of the three above mentioned sources is sufficient to borate the. reactor coolant system to a one percent subcritical margin-in the cold condition at the worst time in core life with a stuck control rod assembly. Minimum volumes of 906 ft' of 1
870) ppm boron as concentrated boric acid solution in the boric acid mix tant or in a reclaimed boric acid storage tank or 60,000 gallons of 2270 ppm boron as boric acid solution in the borated water storage tank will each satisfy this requireaent. -Technical Specification 3.3 assures that at least two of these supplies are available whenever the reactor is critical so that a single failure will r,ot prevent boration to a cold cor.dition. The minimum volumes of boric acid solution given include the boron necessary to account for xenon decay.
j The primary method of adding boron to the reactor coolant system-is to pump the concentrated boric acid solution (8700 ppm boron, minimum) into the makeup tank using either the 10 gpm boric acid pumps or the 30 gpm reclained boric acid pumps. Using only one of the two 10 gpm boric acid pumps, the required volume can be injected 11 less than 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. The alternate method of addition is to inject boric acid from the borated wa'er storage tank using the makeup and purification pumps. The 60,000 gallons of boric acid l
can be injected in less than four hours using only one of the makeup nd purification pumps.
Concentration of boron in the boric acid mix tank or a reclaimed boric acid storage tank may be higher than the concentration which would crystallize at ambient conditions.
For this reason, the boric acid mix tank is provided with an immersion electric heating element and the reciatmed boric acid tanks are provided with low pressure steam heating jackets to maintain the temperature of their contents well above (10*F or more) the crystallization temperature of the boric acid solution contained in them. Both types of heaters are controlled by temperature sensors immersed in the solution contained in the tanks.
Further, all piping, pumps and valves associated with the boric acid mix tank and the reclaimed boric acid storage tanks to transport boric acid solution from them to the makeup and purification system are provided with redundant electrical heat tracing to ensure that the boric acid solution will be maintained 10*F or more above its crystallization temperature. The electrical heat tracing is controlled by the temperature of the external surfaces of the piping systems. Once in the makeup and purification system, the boric acid solution is sufficiently well mixed and (tiluted so that normal system temperatures assure boric acid solubility.
References (1) UFSAR, Section 9.1
" Makeup and Purification System" (2) UFSAR, Section 9.2
" Chemical Addition and Sampling Systems" (3) UFSAR, Figures 6.0-1, 6.0 Simplified ECCS Diagrams 3-20 Amendment No. %, jf( 157,168
Of 4
e.
If an acceptable axial power imbalance is not achieved eithin four hours, reactor power shall be reduced until imbalance limits are met.
f.
Axial powe' imbalance shall be monitored on a minimum frequency of once es y 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.
B.ititi 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. These limits are developed in a manner that ensures the initial condition '.0CA 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 that would cause the Appendix K Criteria to be exceeded should a t0CA occur.
Each limit represents the boundary of operation that will preserve the Acceptance Criteria even if all three limits are at their maximum tllowable values simultaneously.
The effects of the APSRs are included in the limit development. Additional conservatism included in the limit developrannt is introduced by application of:
- a. Nuclear uncertainty factors
- 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.
The incore instrumentation system uncertainties used to develop the axial pcwer imbalance and quadrant tilt limits accounted for various combinations of invalid Self Powered Neutron Detector (SPND) signals.
If the number of valid SPND signals falls below that used in the uncertainty analysis, then another system shall be used for monitoring axial power imbalance and/or quadrant tilt.
3-35a AmendmentNo.J/,Jp,pp,pp,pp,J)p,J/),AAE,JED, 157,168
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7 af 12 0-1000 M*l/stU After 1000 mwd /mtU l.
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Axial Location From Bottom of Core, f t, FIGURE DELETED AND INCORPORATED INTO THE CORE OPERATING-LIMITS REPORT, i
LOCA LIMITED MA11*JM-All,WASLE LINEAR HEAT RATE TM1-1 denamentMo.IM 152.168 3-36b
m 6.9.5.2 The analytical methods used to determine the core operating _linits addressed by the individual Technical Specifications shall be those previously reviewed and approved by 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 Ve sion of PDQ User's Manual," January 1977.
(4) BAW-10ll8A, " 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, "N0ODLE - 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 l
Loop NSS " July 1977.
l (10) BAW-1915P-A, " Bounding Analytical 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 l
1988.
l (12) BAW-10162P-/
TACO-3 Fuel Pin Thermal Analysis Computer Code," Noseniver 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 provided upon issuance for each reload cycle to the NRC Document Control Desk with copies l
to the Regional Administrator and Resident Inspector.
6.10 BEC9RD RETENTIQN 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.
6-19a Amendment No. 72, 77, 129, 137, IAI, 149, 150,168
Q
- f. Changes to procedures required by Specification 6.8.1.
I
- g. Records of solid radioactive shipments.
- h. Test results, in units of microcuries, for leak tests performed on licensed sealed sources.
- i. 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 or 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 inspuctions performed pursuant to these Technical Specifications.
- i. Records of Quality Ascurance 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 l
Amendment No. II, 6%, /2, 77, 129, 141,168 l
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