ML20211B672
| ML20211B672 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 05/30/1986 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20211B676 | List: |
| References | |
| NUDOCS 8606110845 | |
| Download: ML20211B672 (12) | |
Text
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UNITED STAT ES g,.
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-l WASHINGTON,0. C. 20555
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PACIFIC GAS AND ELECTRIC COMPANY '
DIABLO CANYON NUCLEAR POWER PLANT, UNIT I DOCKET NO. 50-275 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 8 License No. DPR-80 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment dated October 30,)1985,(LAR85-13) by Pacific Gas & Electric Company (the licensee complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I;
< B.
The facility wil'1 operate in conformity with the application, as amer:ded, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized a
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 Comission's regulatiens; D.
The issuance of this amendment will not be inimical to the common defense and secuHty or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with.1.0 CFR Part 51 of the Comission's regulations and all applicable requirements bLie been satisfied.
i 2.
Accordingly, tte, license is amended by a change to the combined, Technical Specifications for Units 1 and 2 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:
b 8606110845 860530 PDR ADOCK 05000275 P
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 8, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. PG&E shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment becomes effective at the date of its issuance.
1 FOR THE NU AR ATORY COMMISSION
. bg ctor aven P R Project Direct e #3 Division of PWR Li ing-A, NRR
Attachment:
Changes to the Technical Specifications Date of Issuance: May 30, 1986 l
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION O
j WASHINGTON, D. C. 20555
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 DOCKET NO. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 6 License No. DPR-82 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment dated October 30,1985,(LAR85-13) by Pacific Gas & Electric Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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 a change to the combined Technical Specifications for Units 1 and 2 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:
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. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 6, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.
PG&E shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment becomes effective at the date of its issuance.
F01 THE NUCL ULATORY COMMISSION 1
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ev PWR Project Direct a
Attachment:
Changes to the Technical Specifications Date of Issuance: May 30, 1986 l
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ATTACHMENT TO LICENSE AMENDMENT N05. 8 AND 6 FACILITY OPERATING LICENSE N05. DPR-80 AND DPR-82 DOCKET NOS. 50-275 AND 50-323 Revise the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment Number and contain vertical lines indiciating the area of change.
Remove Pages Insert Pages 3/4 9-15 3/4 9-15 3/4 9-16 3/4 9-17 3/4 9-18 3/4 9-19 B 3/4 9-3 B 3/4 9-3 5-6 5-6 e
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REFUELING OPERATIONS 3/4.9.13 SPENT FUEL SHIPPING CASK MOVEMENT LIMITING CONDITION FOR OPERATION 3.9.13 No spent fuel shipping cask handling operation near the spent fuel pool (i.e., any movement of a cask located north of column line 12.9 for Unit 1 or south of column line 23.1 for Unit 2) shall be performed with fuel in the spent fuel cask exclusion zone identified in Figure 3.9-1.
APPLICABILITY: During all cask handling operations.
ACTION:
With the requirements of the above specification not satisfied, move the cask out of the specified area (s), or move spent fuel from all locations in the racks within the exclusion zone identified in Figure 3.9-1.
SURVEILLANCE REQUIREMENTS I
4.9.13 Racks within the exclusion zone identified in Figure 3.9-1 shall be verified to contain no fuel prior to the movement of the cask into the specified area.
DIABLO CANYON - UNITS 1 & 2 3/4 9-15 Amendment Nos. 8 and 6 l
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Region 1 ll ll ll 41 F
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Cask its E
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FIGURE 3D-1 UNITS 1 AND 2 SPENT FUEL POOL LAYOUT DIABLO CANYON - UNITS 1 & 2 3/4 9-16 Ame'ndment Nos. 8 and 6 i
REFUELING OPERATIONS 3/4.9.14 SPENT FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.14.1 The combination of initial enrichment and cumulative burnup for spent fuel assemblies stored in Region 2 shall be within the acceptable area of Figure 3.9-2.
APPLICABILITY: Whenever fuel assemblies are in the spent fuel pool.
ACTION:
a.
With the requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane operations (with loads in the fuel storage area) and move the non-complying fuel assemblies to Region 1.
Until the requirements of the above specifi-cation are satisfied, boron concentration of the spent fuel pool shall be verified to be greater than or equal to 2000 ppm at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.14.1 The cumulative burnup of each spent fuel assembly stored in Region 2 shall be determined bj analysis of its burnup history, prior to storage in Region 2.
A complete record of such analysis shall be maintained for the time period that the spent fuel assembly remains in Region 2 of the spent fuel pool.
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DIABLO CANYON - UNITS 1 & 2 3/4 9-17 Amendment Nos. 8 and 6
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2.0 2.5 3.0 3.5 4.0 4.5 initial Enrichment, Wt% U-235 i
l FIGURE 3.9-2 1
MINIMUM REQUIRED ASSEMBLY DISCHARGE BURNUP AS A FUNCTION OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 2 DIABLO CANYON - UNITS 1 & 2 3/4 9-18 Amendment Nos. 8 and 6
REFUELING OPERATIONS 3/4.9.14 SPENT FUEL POOL BORON CONCENTRATION LIMITING CONDITION FOR OPERATION,
3.9.14.2 The boron concentration of the spent fuel pool shall be greater than or equal to 2000 ppm.
APPLICABILITY: Whenever fuel assemblies are in the spent fuel pool.
ACTION:
a.
With the requirements of the above specification not satisfied, immediately suspend all movement of fuel assemblies in the spent fuel pool and initiate corrective actions to restore the boron concentration.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.14.2 The boron concentration of the spent fuel pool shall be determined by chemical analysis at least once per 31 days.
DIABLO CANYON - UNITS 1 & 2 3/4 9-19 Amendment Nos. 8 and 6 i
REFUELING OPERATIONS BASES 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM The limitations on the Fuel Handling Building Ventilation System ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.
Transfer of system operation into the iodine removal mode (exhaust through HEPA filters and charcoal adsorbers) is initiated automatically by either the new fuel storage or spent fuel pool area radiation monitors required by Specification 3.3.3.
ANSI N510-1980 will be used as a procedural guide for surveillance testing.
3/4.9.13 ' SPENT FUEL SHIPPING CASK MOVEMENT The restriction on spent fuel shipping cask movement ensures that no fuel assemblies will be ruptured in the event of a spent fuel shipping cask accident.
The dose consequences of this accident are within the dose guideline values of 10 CFR Part 100.
3/4.9.14 SPENT FUEL ASSEMBLY STORAGE The restrictions placed on spent fuel assemblies stored in Region 2 of the spent fuel pool and the requirement for 2000 ppm boron concentration ensure that keff will not be~ greater than 0.95. The spent fuel storage has been designed and analyzed for a maximum enrichment of 4.5 weight percent U-235.
l DIABLO CANYON - UNITS 1 & 2 B 3/4 9-3 Amendment Nos. 8 and 6
DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LdCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY
- 5. 6.1.1 The spent fuel storage racks are designed and shall be maintained with:
A k,ff equivalent to less than or equal to 0.95 when flooded with a.
borated water, which includes a conservative allowance for uncertain-ties as described in Section 9.1 of the FSAR.
b.
A nominal 10.93 inch center-to-center distance between fuel l
assemblies placed in the storage racks.
l 5.6.1.2 The k,ff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.90 when flooded with unborated water.
DRAINAGE l
5.6.2 The spent fuel storage pool is designed and shall be maintained to I
prevent inadvertent draining of the pool below elevation 133.
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CAPACITY 5.6.3 The spent fuel storage poc1 is designed and shall be maintained with a storage capacity limited to no more than 1324 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
l Amendment Nos. 8 and 6 l
DIABLO CANYON - UNITS 1 & 2 5-6
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