ML20210C561
| ML20210C561 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/29/1987 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210C566 | List: |
| References | |
| NUDOCS 8705060229 | |
| Download: ML20210C561 (7) | |
Text
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UNITED STATES o
NUCLEAR REGULATORY COMMISSION L
E WASHINGTON,0. C. 20555
.a BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 107 License No. OPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated July 31, 1986, as supplemented January 21, 1987, 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 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 l
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.
8705060229 870429 PDR ADOCK 05000318
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- 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-69 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in. Appendix A, as revised through Amendment No.107, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its isseance.
FOR THE NUCLEAR REGULATORY COMMISSION 7.Lso_.C a Robert A. Capra, Acting Director Project Directorate I-1 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: April 29, 1987
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e ATTACHMENT TO LICENSE AMENDMENT N0.107 '
FACILTIY OPERATING LICENSE NO.~DPR-69 DOCKET NO.'50-318 Replace 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 indicating the areas of change.
The corresponding overleaf pages are provided to maintain document completeness.
- Remove Pages Insert Pages 3/4 7-9 3/4 7-9 8 3/4 7-3 8 3/4 7-3
' B 3/4 7-4 B 3/4 7-4 (No change, repositioned.)
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O PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
With one main steam line isolation valve inoperable, MODE 1 POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in HOT SHUTDOWN within the
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next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With one main steam line isolation valve inoperable, sub-MODES 2 and 3 sequent operation in MODES 1, 2 or 3 may proceed provided:
a.
The isolation valve is maintained closed.
b.
The provisions of Specification 3.0.4 are not applicable.
Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.5 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within 5.2 seconds when tested l
pursuant to Specification 4.0.5.
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0 CALVERT CLIFFS-UNIT 2 3/47-9 Amendment No.107
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I CALVERT CLIFFS - UNIT 2 3/4 7-10 Amendment No. 76. 47, 107
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PLANT SYSTEMS
,7, BASES l
3/4.7.1.3 ' CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage. tank with the minimum water
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volume ensures that sufficient water is available.to maintain the RCS at HOT
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STANDBY conditions for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with steam discharge to atmosphere with concurrent and total loss of offsite power.. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
3/4i7.1.4 ACTIVITY-i The limitations on. secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also.
includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the. steam generator of the affected steam line and a concurrent loss of offsite electrical power. These values are consistent with the assumptions used in the accident analyses.
3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) nhnimize the positive' reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line r
rupture occurs within containment. The OPERABILITY of the main steam isola-tion valves within the closure times of the surveillance requirements are 1
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consistent with the assumptions used in the accident analyses. The main steam isolation valves are surveilled to close in-less than 5.2 seconds to ensure that under reverse steam flow conditions, the valves will close in less than j
the 6.0 seconds assumed in the accident analysis.
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3/4.7.1.6 SECONDARY WATER CHEMISTRY The secondary water chemistry program is designed to provide maximum j
protection to both the steam generator and secondary: system internals. The-i most damaging chemical reactants enter the system via condenser cooling j
water ingress. - Accumulation of these impurities in the steam generators may lead to loss of metallurgical integrity and/or eventual component failure.
The limits presented in Table 3.7-3 are those prescribed by the NSSS supplier as " limited-operation" chemistry parameters and are consistent with the most recent industry standards. By routine monitoring of' these parameters, plant personnel are able to rapidly detect and limit the duration of ingress of i
chemically detrimental species and thereby maintain steam generator tube 4
integri ty.
3/4.7.2 STEAM GENERATOR PRESSURE /TEMPE MTURE LIMITATION-The limitation on steam generator pressure and temperature ensures that <
the pressure induced stresses in the steam generators do not exceed the
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CALVERT CLIFFS - UNIT 2 B 3/4 7-3 Amendment No. J5,#9.55, 107 I
A g PLANT SYSTEMS BASES I
maximum allowable fracture toughness stress limits. The limitations of 90 F-and 200 psig are based on steam generator secondary side limitations and are sufficient to prevent brittle fracture.
3/4.7.3 COMP 0NENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3/4.7.4 SERVICE WATER SYSTEM The OPERABILITY of the service water system ensures that sufficient cooling capacity is available for continued operation of equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3/4.7.5 SALT WATER SYSTEM The OPERABILITY of the salt water system ensures that sufficient cooling capacity is available for continued operation of equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERA-BILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 10 of Appendix-
"A",10 CFR Part 50.
3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM The OPERABILITY of the ECCS pump room exhaust air filtration system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the CALVERT CLIFFS - UNIT 2 B 3/4 7-4 Amendment No. 107
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