ML20149H073
| ML20149H073 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 10/31/1994 |
| From: | Peterson S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149H076 | List: |
| References | |
| NUDOCS 9411100018 | |
| Download: ML20149H073 (9) | |
Text
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a pnMav 21 UNITED STATES ee s
g NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20565 4001
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PACIFIC GAS AND ELECTRIC COMPANY DOCKET N0. 50-275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. DPR-80 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee) dated February 16, 1994, 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 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.
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:
9411100010 941031 PDR ADOCK 05000275 p
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 96, are hereby incorporated in the license.
Pacific Gas & 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 60 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION u h.
MN Sheri R. Peterson, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of Issuance:
October 31, 1994
. p*Mo u y
t UNITED STATES
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20666 4001 s...../
PACIFIC GAS AND ELECTRIC COMPANY DOCKET N0'. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. DPR-82 1.
The Nuclear Regulatory Commission (the Commission) has found that A.
The application for amendment by Pacific Gas & Electric Company (the licensee) dated February 16, 1994, 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 i
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 liealth.
t and safety of the public, and (ii) that such activities will be I
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; i
1 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.
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:
1
(2)
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 95, are hereby incorporated in the license.
Pacific Gas & 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 60 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h
Sheri R. Peterson, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 31, 1994
N*
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.96 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 95 TO FACILITY OPERATING LICENSE NO. DPR-82 DOCKET NOS. 50-275 AND 50-323 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages are also included, as appropriate.
REMOVE INSERT 3/4 2-8 3/4 2-8 6-18 6-18 1
1 EQWER DISTRIBUTION LIMITS l
SURVE!LLANCE RE0VIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2 F (z) shall be evaluated to determine if F,(z) is within its limits i
a by:
a.
Using the moveable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.
Increasing the measured F z) component of the power distribution b.
map by 3% to account for,(anufacturing tolerances and further m
increasing the value by 5% to account for measurement uncertainties.
c.
Satisfying the following relationship:
pRTP F,"(z) s o x Kfz) for P > 0.5 P x W(z) pRTP F,"(z) s o x K(z) for P s 0.5 W(z) x 0.5 where F "(z) is the measured F,(z) increased by the allowances for o
manufacturing tolerances and measurement uncertainty, F,"'" is the F, limit, K(z) is the normalized F,(z) as a function of core height, P is the relative THERMAL POWER, and W(z) is the cycle dependent function that accounts for p"ower distribution transients encountered during normal operation.
F, '", K(z), and W(z) are specified in the COLR.
d.
Measuring F,"(z) according to the following schedule:
1.
Upon achieving equilibrium conditions after exceeding by 20% or more of RATED THERMAL POWER, the THERMAL POWER at which F,(z) was last determined,* or 2.
At least once per 31 Effective Full Power Days (EFPD), whichev-er occurs first.
e.
With measurements indicating maximum F,"(z) over z K(z) has increased since the previous determination of F,"(z) either of the following actions shall be taken:
- During power escalation at the beginning of each cycle, power level may be increased until a power levei for extended operation has been achieved and a power distribution map obtained.
DIABLO CANYON - UNITS 1 & 2 3/4 2-7 Amendment Nos. 45 & it, 71 & 70
POWER DISTRIBUTION LIMITS SURVEILLANCE REOUIREMENTS (Continued)
M 1)
FQ(z) shall be increased over that specified in Specification 4.2.2.2.c by an appropriate factor specified in ibe COLR, or M
2)
FQ(z) shall be measured at least once per 7 EFP0 until two succetsive maps indicate that maximum FM(z) 0 is not increasing.
over z K(z) f.
With the relationship specified in Specification 4.2.2.2.c above not being satisfied:
1)
Calculate the percent FQ(z) exceeds it limit by the following expression:
F $2) x Wzfkl q
x 100 for P > 0.5 y
2 N
(\\
F h x K(I) )"
/'maximun M
~
( evsr 2 0()
N) h-1 x 100 for P < 0.5 p IP k
K s
- K(z)
.5 2.
Either one of the following actions shall be taken:
a)
Place the core in an equilibrium condition where the limit in Specification 4.2.2.2.c is satisfied.
Power level may then be increased provided the AFD limits of Specification 3.2.1 are reduced 1% AFD for each percent FQ(z) exceeds its limit, or DIABLO CANYON - UNITS 1 & 2 3/4 2-8 Amendment Nos. 45 1 14, 71 1 70, 96 & 95
ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) rem exposure according to work and job functions,* e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special mainte-nance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosi-meter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8 will be included in the annual report. The following information shall be included:
(1) reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radioiodine concentrations; (3) clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) graph of the I-131 concentration and one other radiciodine isotope concentration in micro-curies per gram as a function of time for the duration of specific activity above the steady-state level; and (5) the time duration when the specific activity of the primary coolant exceeded the radiciodine limit.
MNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT **
6.9.1.5 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
The report shall include summaries, interpreta-tions, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the RMCP and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
J
- This tabulation supplements the requirements of 10 CFR 20.407.
- A single submittal may be made for a multiple unit plant.
DIABLO CANYON - UNITS 1 & 2 6-17 Amendment Nos. 67 & 66
ADMINISTRATIVE CONTROLS ANNUAL RADI0 ACTIVE EFFLVENT RELEASE REPORT
- 6.9.1.6 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include a summary of the quantities of radio-active liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the RMCP and PCP, (2) in conformance with 10 CFR 50.36a and Section IV.B.1 Appendix I to 10 CFR Part 50.
MONTHLY OPERATING REPORT 6.9.1.7 Routiae reports of operating statistics and shutdown experience, including documentation of all challenges and failures to the PORVs or safety valves, shall be submitted on a monthly basis to the NRC in accordance with 10 CFR 50.4, no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.8.a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
1.
Shutdown Rod Insertion Limits for Specification 3/4.1.3.5, 2.
Control Rod Insertion Limits for Specification 3/4.1.3.6, 3.
Axial Flux Difference for Specification 3/4.2.1, I
4.
Heat Flux Hot Channel Factor, K(Z) and W(Z) - F (z) (F"'" for a
Specification 3/4.2.2), and 5.
RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor -
FL (Fs" and PF, for Specification 3/4.2.3).
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
1.
WCAP-10216-P-A, Revision IA, Relaxation of Constant Axial Offset Control F Surveillance Technical Specification, o
February 1994 (Westinghouse Proprietary),
2.
WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985 (Westinghouse Proprietary),
- A single submittal may be made for a multiple unit plant. The submittal should combine those sections that are common to all units at the plant; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
DIABLO CANYON - UNITS 1 & 2 6-18 Amendment Nos. Tr7 &-6fr, it &40; 38-& 11;- 96 & 95
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