ML20203L293
| ML20203L293 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  (DPR-80-A-121, DPR-82-A-119) |
| Issue date: | 02/13/1998 |
| From: | Steven Bloom NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203L297 | List: |
| References | |
| NUDOCS 9803050437 | |
| Download: ML20203L293 (9) | |
Text
.
s**t'og lt UNITED STATES po
- f j
NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 2066 Hoot
\\ *-
/
...+
PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DMBLO CANYON NUCLEAR POWER PLANT. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICEtEE Amendment No.121 License No. DPR 80 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas and Electric Company (the licensee) dated May 14,1997, as supplemented by letter dated December 15, 1997, complies with the standards and requirements of the Atoirile Energy Act of 1954, as amended (the Act), and the Commission's regulatice.3 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 publiu, 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 w'tr.10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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-80 is hereby amended to read as follows:
90030!'0437 900213 PDR ADOCK 05000275 P
PDR A
2 (2)
TechnicALERt.CiftCal!QD1 The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 121, are hereby incorporated in the license. Pacific Gas and Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of its date of issuance to be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L
,l t
/ even D. Bloom, Project Manager St Project Directorate IV 2 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
February 13, 1998
- Gv e*
4 UNITED STATES LLf/ j NUCLEAR REGULATORY COMMIDSION WASHINGTON, D.C. 20MH001 4.....-
l PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWEB PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 119 License No. DPR 82 1.
The Nuclear Regulatory Commission (the Commicslon) has found that:
A.
The application for amendment by Pacific Gas and Electric Company (the licensee) dated May 14,1997, as supplemented by letter dated December 15, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 reasonaole 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 si of the Commission's regulations and all applicable vequirements have been satisfied.
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 82 is hereby amended to read as follows:
2 (2)
Igchnical Softelfications The Technical Specifications contained in Appendix A and the Environmental Protectio. Plan contained in Appendix B, as revised through Amendment No. 119. are hereby incorporated in the license. Pacific Gas and Electric Company shall operate the facility in accordance with the Technical l
Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
Thit license amendment is effective as of its date of issuance to be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (0
%2 L.
'A s
St 'ven D. Bloom, Project Manager Project Directorate IV 2 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 13, 1998
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.121 TO FACILITY OPERATING LICENSE NO. DPR 80 AND AMENDMENT NO.119 TO FACILITY OPERATING LICENSE NO. DPR 82 DOCKET NOS. 50 275 AND 50 323 Revise Appendix A Technical Specifications by removing the pages identifed below and inserting the enclosed pages. The revised pages are identified by Amendment number and contain marginallines indicating the areas of change, The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT B 3/4 2 1 B 3/4 2 1 B 3/4 2 2 B 3/4 2 2 6 19 6 19
_m
2L4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance of fuel Integrity during Condition 1 (Normal Operation) and 11 (Incidents of Moderate frequency) events by:
(a) maintaining the minimum DNBR in the core greater than or equal to 1.30 during normal operation and in short term transients, and (b) limiting the fission gas release, fuel pellet temperature and cladding mechanical properties to within assumed design cr1teria.
In addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and that there is a high level of probability that the ECCS acceptance criteria limit of 2200*f is not exceeded.
The defin1tions of certain hot channel and peaking factors as used in these specifications are as follows:
F,(Z)
Heat Flux Hot Channel factor, is defined as the maximum local heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods:
F%
Nuclear Enthalpy Rise Hot Channel _ Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power; and f (Z)
Radial Peaking Factor, is defined as the ratio of peak power y
density to average power density in the horizontal plane at core elevation Z.
3/4.2 1 AX1AL FLUX DIFFERENCE 1he limit envelope of F 'j"on AXIAL FLUX DIFFERENCE assure that the F,(Z) upper bound times the normalized axial peaking factor is not exceeded during either, normal operation or in the event of xenon redistribution following power changes.
Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm.
The computer determines the one minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for at least 2 of 4 or 2 of 3 OPEPABLE excore channels are outside the AFD limits and the THERMAL POWER is l
greater than 50 percent of RATED THERMAL POWER.
l l
DIABLO CANYON UNITS 1 & 2 B 3/4 2-1 Un1t 1 Amendment No M 121 Unit 2 - Amendment No. M.119 I
I m
4 POWER DISTRIBUTION LIMITS e
BASES 3/4.?.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE AND NUCL EAR ENTHALPY R15E HOT CHANNLL FACTOR The limits on Heat Flux Hot Channel Factor, RCS Flowrate, and Nuclear Enthalpy Rise Hot Channel Factor ensure that:
(1) the design limits on peak local power density and minimum DNBR are not exceeded, and (2) in the event of a LOCA there is a high level of probability that the peak fuel clad l
temperature will not exceed the 2200*F ECCS acceptance criteria limit.
DIABLO CANYON - UNITS 1 & 2 B 3/4 2-2 Unit 1 - Amendment No. 12.121 Unit 2 - Amendment No. 40,119
E'lSTRATIVf CONTROLS CORE OPERATING LIMITS REPORT (Continued) 3.
WCAP 8385, Power Distribution Control and Load Following Procedures, September 1974 (Westinghouse Proprietary),
4.
WCAP 10054 P A, Westinghouse Small Break LOCA ECCS Evaluation Model Using the NOTRUMA Code, August 1985.
(Westinghouse Proprietary), and 5.
WCAP 12945 P. Westinghouse Code Qualification Document for Best Estimate loss of Coolant Analysis, June 1996 (Westinghouse Proprietary)
- c.
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal mechanicdl limits, core thermal lydraulic limits ECCS limits, such as SHUTDOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met.
d.
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 to the Regional Administrator and Resident inspector.
SPECIAL REPORTS 6.9.2 S)ecial reports shall be submitted to the NRC in accordance with 10 CFR 50.4 wit 11n the time period specified for each report.
6 10 RECORD RETENTION 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.
6.10.1 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 lots of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety; c.
ALL REPORTABLE EVENTS:
- As evaluated in NRC Safety Evaluation dated February 13, 1998.
l DIABLO CANYON UNITS 1 & 2 6 19 Unit 1 - Amendment No. (4-d4.121 Unit 2 - Amendment No. %@.119
- - _. ~. - _ _ -
_ _.. -. _. -.. ~ -. _..
_ _ ~ -. -
e ADMINISTRATIVE CONTROLS RECORDRETENTION(Continued) d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications; e.
Records of changes made to procedures required by Specification 6.0.1 f.
Records of radioactive shipments g.
Records of sealed source and fission detector leak tests and results; and h.
Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the unit Operating Licenses a.
Records and drawing changes reflecting unit design modifications made to systeres and equipment described in the Final safety Analysis Reports b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories c.
Records of radiation exposure for all individuals entering radiation control areast d.
Records of gasecus and liquid radioactive material released to the environst Records of transient or operational cycles for those unit coa.ponents e.
identified in Table 5.7-1; f.
Records of reactor tests and experiments:
g.
Records of training and qualificatisii 'or currsH members of the unit staffs h.
Records of in-service inspections performed purwant to these Technical $pecificatiotis
- 1. *; Records of Quality Assurance activities required by the QA Manua J.
Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.5pg k.
Records of meetings of the PSRC and N50Cp l
4 DIABLO CANYON - UNITS 1 & 2 6-20 Amendment Nos.68 and 67
. -