ML20036B082
| ML20036B082 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 05/12/1993 |
| From: | Frizzle C Maine Yankee |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20036B083 | List: |
| References | |
| CDF-93-73, MN-93-52, NUDOCS 9305180142 | |
| Download: ML20036B082 (4) | |
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MaineYankee RELIABLE ELECTRtCtTY FOR MAINE $lNCE 1977 Cha tes D Fr.:zle Edson Dr've Presden!
Aagasta, Maine o4336 (207) 622-4868 May 12, 1993 MN-93-52 CDF-93-73 Proposed Change No. 178 l
UNITED STATES NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Washington, DC 20555
References:
(a)
License No. DPR-36 (Docket No. 50-309)
(b) USNRC Letter to MYAPCo of December 4,1992 (c) MYAPCo Letter to USNRC of March 4,1993 (MN-93-23) l
Subject:
Proposed Technical Specification Change No.178 - Environmental Monitors Surveillance Requirements Gentlemen:
Maine Yankee hereby submits, pursuant to 10CFR50.90, this application to amend Specification 4.1, Instrumentation and Control, of the Maine Yankee Technical Specifications. This proposed change would delete the surveillance requirements for the Environmental Monitors.
Presently, the surveillance requirements for the Environmental Monitors are specified in Item 5 of Table 4.1-3, " Minimum Frequencies for Checks, Calibrations, and Testing of Miscellaneous Instrumentation and Controls".
By reference (b), the NRC approved relocation of the Radiological Environmental Monitoring Program requirements from Technical Specifications to the Off-Site Dose Calculation Manual (ODCM). As Environmental Monitor surveillance requirements are l
now specified in a procedure required by the ODCM, there is no need for duplicative i
Technical Specification surveillance requirements.
l A description of the proposed changes and a summary of the Significant Hazards i
Evaluation is presented in Attachment A. As discussed in the attachment, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of l
accident from any accident previously evaluated, or involve a significant reduction t
in a margin of safety.
Thus, based.on this evaluation, it is concluded that there is reasonable assurance that operation of the Maine Yankee plant, consistent with the proposed. Technical Specifications, will not impact the health and safety of the public.
t Revised Technical Specification page 4.1-10 is included as Attachment B.
Proposed Change No.175, submitted separately by Reference (c), changed item 3 of this table.
This proposed change has been reviewed and approved by the Plant Operation and Review Committee. The Nuclear Safety Audit and Review Committee has also reviewed this submittal. The State of Maine Nuclear Safety Inspector reviewed this request in draft form and is receiving a copy of this submittal.
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Mainennkee UNIT $D STATES NUCLEAR REGULATORY COMMISSION MN-93-52 Attention: Document Control Desk Page 2 We request that this proposed change be made effective within 30 days after issuance.
Very truly yours,
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Charles D. Frizzle President and Chief Executive Officer JHA/ jag Attachments c:
Mr. Thomas T. Martin Mr. E. H. Trottier Mr. Charles S. Marschall Mr. Clough Toppan Mr. Patrick Dostie STATE OF MAINE Then personally h Pared before me, Charles D. Frizzle, who being duly sworn did state that he is Presiat t and Chief Executive Officer of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing request in the name and on behalf of Maine Yankee Atomic Power Capany, and that the statements th2 rein are true to the best of his knowledge and belief.
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/ Notary Public BARBARA J. PADAVAta NOTARY PUBUO.MAWE MYCCMAsSION EXPiFESJJNE 20,1MS s
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I ATTACHMENT A j
Description of Chance
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The Environmental Monitors referred to in Table 4.1-3, Item 5 are the i
environmental air samplers designed to monitor the atmosphere at several locations around the plant. These samplers provide a way to assess the presence of airborne f
radioiodine and radioactive particulates from all sources including plant effluents
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by passing a quantifiable amount of air through charcoal and particulate filters.
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In response to Generic Letter 89-01, Technical Specifications were amended by I
Reference (b) to reloccte the Radiological Environmental Monitoring Program (REMP) requirements from Technical Specifications to the Off-Site Dose Calculation Manual l
(ODCM). The surveillance requirements for the air samplers were not relocated with l
other Technical Specification requirements during this Radiological Environmental Technical Specification (RElS) change to other controlling documents because they 4
predated the RETS changes. As indicated in the cover letter, this proposed change d
would delete the entry, Environmental Monitor, Item 5 of Table 4.1-3, of the Maine Yankee Technical Specifications as it is now duplicated in a procedure required by the ODCH.
I The assessment of airborne radioactive particulate and radioiodine constituents l
through the use of air samplers is one component of the REMP. Maine Yankee Technical j
Specifications (Section 5.8.1) require procedures for implementation of the ODCM.
t Procedure 26.1, Radiological Environmental Monitoring Program, describes the l
programmatic aspects and responsibilities for implementation of the REMP.
Surveillance requirements for monthly flow checks and annual calibrations of the air j
samplers are required by Procedures 26.1 and 26.301. Procedure 26.1 specifies that i
flow checks and calibrations be performed in accordance with Procedure 26.301, Environmental Media Sample Collection Methods. Procedure 26-301 requires a monthly i
check and annual calibration of the air samplers.
i Finally, " Standard Technical Specifications: Combustion Engineering Plants" 1
(NUREG-1432, Vol.1, September 1992) follow the format of Maine Yankee Technical Specifications referencing the ODCM and plant procedures for details of the REMP with no specific reference to calibrations or checks of environmental monitors or samplers.
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4 Sianificant Hazards Evaluation i
The proposed change to Technical Specifications Table 4.1-3 has been evaluated against the standards of 10 CFR 50.92, and has been determined not to involve a l
significant hazards consideration. Therefore, implementation of the change does not:
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Involve a significant increase in the probability or consequence of an accident previously evaluated.
The FSAR accident conditions and assumptions are not affected by the proposed Technical Specification change.
The proposed change does not involve a test, experiment, or a l
modification to a system. The proposed change is administrative in nature and does not increase the probability of occurrence of an accident previously evaluated.
The change deletes reference to checks and calibrations of monitors because they are now contained in a separate l
procedure.
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Create the possibility of a new or different kind of accident from any 1
accident evaluated previously.
The FSAR accident conditions and assumptions are not affected by the proposed Technical Specification change. The proposed change does not involve a test or experiment, or a modification to a system and does not affect any plant equipment or i
operation procedures which could create the possibility of a different accident. The proposed change is administrative in nature and involves no i
accident scenario.
On matters related to nuclear safety, all accidents are bounded by previous analyses and no new accidents are involved.
3.
Involve a significant reduction in a margin of safety.
The proposed Technical Specification change does not affect any operating practices or l
j limits nor any equipment or system important to safety.
The proposed l
change is administrative in nature and will not reduce a margin of safety.
Based on the above, it is concluded that there is reasonable assurance that i
operation of the Maine Yankee plant, consistent with the proposed Technical e
i Specifications, will not endanger the health and safety of the public.
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