ML20070C071
| ML20070C071 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/14/1991 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070C074 | List: |
| References | |
| NUDOCS 9102210150 | |
| Download: ML20070C071 (4) | |
Text
.
7590-01 L..lTED STATES NUCLEAR PEGULATORY COMMISSION BALTlHORE GAS AND ELECTRIC COMPAllY DOCKET NO. 50-317 EllV!KONMENTAL ASSES $t'ENT AND FINDING OF t:0 SIGNIF_ICAllT IMPACT The U. S. fluclear Regulatory Comission (the Commission) is considering
?ssuance of an exemption from certain requirements of 10 CFR part 50, Appendix 0, paragraph !!I.D.3, Type C Tests,* to the Baltimore Gas and Electric Company (BC&E/ licensee) for the Calvert Cliffs fluclear Power Plant, Unit 1, located at the licensee's site in Calvert County, Maryland.
ENVIRONMENTALASSES$tiENT
,ldentification of Proposed Action: The licensee would be exempt from the requirement of 10 CFR Part 50, paragraph 111.D.3, to the extent that a one-time extension from March 23, 1991, to June 21,1991, (apprcximately three months) would be allowed for performing a type C local leak rate test (LLRT) on containment isolation valve 1-CVC-515 which is currently required at intervals no greater than 2 years.
This rcquested extension will allow the valve to be LLRT with the rest of the Unit 1 containment isolation valves which are due for testing in June 1991, thus, placing 1-CVC-515 LLRT interval back into sequence with the rest of the Unit I containment isolation valves requiring LLRTs in accordance with the 2 year schedule of the above cited regulation.
The exemption is responsive to the licensee's application for exemption dated January 18, 1991.
l l
9102210150 910214 DR-ADOCK 050 7
J
The Need for the proposed Action: Maintenance was performed on the valve in March of 1989 which resulted in the requirea LLRT being performed three months earlier than the other Unit 1 containment isolation valves which require the LLRTs in accordance with the schedule of the above cited regulation.
This was initially considered acceptable by the licensee based on the schedule for the Unit 1 spring 1991 outage and projected startup of Unit 2.
However, due to area electrical power needs, the pennsylvania Hew Jersey-Maryland (pJM) Hetwork requested that the licensee not shut down Unit 1 until late in March.
In addition, subsequent delays in the startup of Unit 2 would result in conflicts for the licensee's plant staff to provide optimal support for the initiel startup process for Unit 2 and shutdown of Unit 1.
The reouested extension will provide the li:ensee flexibility to perform its Unit 1 outage tasks while also allowing for improved coordination of plant staff to support both units in a safe and efficient manner.
The proposed exemption constitutes approximately a three month delay in performing the Type C test (LLRT) on containment isolation valve 1-CVC-515. As noted, the extension will accommodate the current schedules for both Units, allow the licensee flexibility to perform required tasks, and also allow for improved coordination of the plant staff to support activities of both units in a safe and efficient manner.
.The required LLRTs have been performed in accordance with the required schedule specified in the regulations during previous planned outages.
The initial planning and scheduling allowed for the 1-CVC-515 valve to be tested in the upcoming outage and returned to the same sequences as the other valves.
However, the unanticipated supply requirements and schedule changes for both units have necessitated the one-time extension request.
Based on past performance and existing circemstances, a good faith effort has been made.
L
3-Environn, ental Impact of the Proresed tction:
The proposed exemotion will not change plant equipment, operation or procedures, and does not adversely affect either the probability or the consequences of any accident at this f acility.
The exemption does not affect radiolegice; c11)Ler.ts from the f acility or radiation levels at the f acility. Therefore, the Conniscion concludes that there are no significent radiological environmental impacts associated with the proposed exemption.
The proposed exemption does not effect nonradiological plant effluents and has no other environmental impact.
Therefore, the Commission concludes that there are no significant nonradiological environmental impacts associatrd with
- Le preposed exemption.
t.lternadise to '.ht h cpusto Act ior..
Sinct the Coninission has concluded there are r.o measurable environmental impacts a.esociated with the proposed exemption, any alternatives with equal or greater environmental impact need not be evaluated. The principal alternative to the exemption would be to require rigid compliance with the schedular reouirements of 10 CFR Part 50, Apoendix 0, Paragraoh III.D 3, for performing the LLRT on containment isolation valve 1-CVC-515. Such action would not enhance the protection of the environaent.
Alternative Use of Resources: This ection involves no use of resources not 1
i previously considered in the Final Envirenmental Stetenient of the Calvert Cliffs Nuclear Power Plant, Unit 3.
l l
l l
l
4.
Agencies and Persons Consulted: The NRC staff reveiwed the licensee's request and did not consult other agencies or persons.
FINDING OF NO SIGNIFICANT IMPACT: The Commission has determined not to prepare an environmental impact statement for the proposed license amendr.ent.
Based upon the for(991ng environmental assessment, we conclude that the proposed action will not have a significant effect on the quality of the human environment.
For further details with respect to this action, see the licensee's letter dated January 18, 1991. This letter is available for public inspection at the Comalssion's Public Document Room, 2120 L Street, N.W., Washington, D.C., and at the Calvert County Library, Prince Frederick, Maryland.
Dated at Rockville, Maryland, this 14th day of February 1991.
FOR THE NUCLEAR REGULATORY COMMISSION Nol.fo.( W Robert A. Capra, Director Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation m
m_____w
"