ML20212C021

Application for Amend to License DPR-36,consisting of Proposed Change 124,revising Tech Specs Re Reporting Requirements for Primary Coolant Sys Iodine Spikes,Per Generic Ltr 85-19.Related Info Encl.Fee Paid

ML20212C021
Person / Time
Site:	Maine Yankee
Issue date:	07/29/1986
From:	Randazza J Maine Yankee
To:	NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation
Shared Package
ML20212C025	List: ML20212C021 ML20212C028
References
GL-85-19, MN-86-76, NUDOCS 8608070301
Download: ML20212C021 (5)

Text

l MAIRE 9ARHEE ATOIRICPOWERCOMPARSe ,uaug7,y,is?gTa",'s h (207) 623-3521 e

July 29, 1986 MN-86-76 Proposed Change #124 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk

References:

(a) License No. DPR-36 (Docket No. 50-309)

(b) MYAPCo Letter to USNRC dated January 29, 1986 (MN-86-11)

Proposed Change #115 (c) USNRC Generic Letter 85-19, Reporting Requirements on Primary Coolant Iodine Spikes, dated September 27, 1985 (d) USNRC Letter to MYAPCo dated May 14, 1986, Request for Additional Information on Proposed Change #115

Subject:

Proposed Change #124 to the Maine Yankee Technical Specifications:

Reporting Requirements Gentlemen:

At the suggestion of your staff, this portion of Reference (b) is being submitted as a separate amendment request to facilitate processing. The remaining portions of Reference (b) will be resubmitted for clarity.

A description of the proposed changes is included in Attachment A.

In summary, this proposed change incorporates the specific reporting requirements for iodine spiking into the annual report as recommended in Generic Letter 85-19 and deletes the primary coolant iodine activity report from Technical Specification 5.9.1.7, Special Reports, since this aspect of plant operation would be reported on an annual basis pursuant to the proposed Technical Specification 5.9.1.3.

! He have concluded that the proposed change is primarily administrative in nature and that the operation of Maine Yankee in accordance with the proposed change would not:

1. Involve a significant increase in the probability or consequences of an accident previously analyzed; or oo l

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MAtNE YANKEE ATOMIC POWER COMPANY United States Nuclear Regulatory Commission Page Two Attention: Document Control Desk MN-86-76

2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety, Therefore, this proposed change does not involve a significant hazards consideration (Attachment B).

Revised pages to the Technical Specifications and replacement instructions are contained in Attachment C. These changes address the information requested in Reference (d).

The contents of this proposed change has been reviewed by the Plant Or,erations Review Committee and the Nuclear Safety Audit and Review Committee. A copy of this proposed change has been sent to a representative of the State of Maine.

A license amendment application fee of $150.00 is enclosed.

He request that the amendment becomes effective on the date of issuance.

Very truly yours, MAINE YANKEE ATOMIC P0HER COMPANY John B. Randazza Executive Vice President JBR/bjp Attachments cc: Mr. Ashok C. Thadani Dr. Thomas E. Murley Mr. Cornelius F. Holden Mr. Pat Sears Mr. Clough Toppan STATE OF MAINE Then personally appeared before me, John B. Randazza, who being duly sworn did state that he is Executive Vice President 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 Company, and that the statements therein are true to the best of his knowledge and belief.

f /hotary Public RY PUB IC IN WY COMMiZION EXPm;S OCTOBER 3.1992 7650L-SOE

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MAINE YANKEE ATOMIC POWER COMPANY I

I ATTACHMENT A Descriotion of Chanaes The proposed change would revise Technical Specification 3.2, as recommended and endorsed in Generic Letter 85-19 (Reporting Requirements on Primary Coolant System Iodine Spikes) as follows: 3

a. Elimination of the existing Remedial Action Step 1, which calls for the reactor to be subcritical within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if the primary coolant system specific activity is greater than 1.0 uC1/ gram Dose Equivalent I-131 (DEI) for more than 800 cumulative hours in any period of 12 consecutive months.

b. Elimination of the existing Remedial Action Step 2 which requires that if the primary coolant specific activity is greater than 1.0 uCi/ gram Dose Equivalent I-131 for more than 500 cumulative hours in any period of 6 consecutive months, a report must be sent to the Commission within 30 days indicating the number of hours above this limit.

c. The reporting requirements of Technical Specification 3.2.C which presently requires a report to be sub:nitted to the Commission within 30 days of exceeding 1.0 uCi/ gram DEI or 100/E uCi/ gram along with other information on plant operating characteristics, have been replaced with an annual reporting requirement endorsed by Reference (c) to reduce unnecessary reporting requirements.

Specification 5.9.13, Annual Reports, has been revised accordingly, and the contents of the reporting requirements are as detailed in Generic Letter 85-19.

d. Figure 3.2-1 is proposed to be incorporated in Technical Specification 3.2 as recommended in Generic Letter 85-19. This

figure, from NUREG-0212, Revision 2, Standard Technical ll Specifications for Combustion Engineering Pressurized Hater Reactors, l shows acceptable and unacceptable operating regions regarding RCS l dose equivalent I-131 concentration as a function of power level.

( Hith this curve, the current specification limit for iodine spikes not greater than 60 uC1/ gram DEI-131 will continue in effect at or

above 80% rated thermal power. The limit of iodine spiking on the l Figure 3.2-1 increases below 80% rated thermal power; this has been l found to be generically acceptable by the NRC staff for other Combustion Engineering plants.

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i ATTACHMENT B 4

SIGNIFICANT HAZARDS EVALUATION t

f Operation of the Maine Yankee plant in accordance with this change to its

, operating license has been evaluated using the standards in 10 CFR 50.92 L regarding no significant hazards consideration. This proposed change does not involve a significant hazards consideration because operation of Maine Yankee g in the proposed manner would not:

a. Involve a significant increase in the probability or consequences of an accident previously evaluated.

i' The elimination of the current Remedial Action Steps 1 and 2 of Technical Specification 3.2 requiring a plant shutdown if the coolant iodine activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12 month period and 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in a 6 month period, respectively, does not significantly increase either the probability or the consequences of

a previously evaluated accident.

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The consequences of an accident analyzed with elevated coolant activity is bounded by analyses of applicable accidents assuming a pre-existing iodine spike of 60 uCi/ gram dose equivalent I-131 activity.

! The probability of previously evaluated accident is not significantly increased by the duration of the elevated coolant iodine activity.

Proper fuel management ensures that appropriate actions would be taken in the event the Technical Specification iodine limit was exceeded to ensure that fuel cladding integrity would be maintained with design limits and preclude any possibility of 800 cumulative hours of coolant iodine activity above the Technical Specification limit. The NRC staff has determined, Reference (c), that this Technical Specification requirement (shutdown if coolant iodine activity limits are exceeded for 800 cumulative hours in a 12 month period) is unnecessary and can be eliminated.

The remaining changes relax the special 30 day reporting requirements for iodine spikes to an annual report consistent with the guidance of l Generic Letter 85-19. These are administrative changes and do not l

affect the probability or consequences of an accident previously ,

I evaluated.

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MolME VANKFE ATOMIC POWER COMPANY

b. Create the possibility of a new or different kind of accident from any previously analyzed.

The operating limits and sampling requirements for coolant iodine activity have not been altered by the proposed changes. Therefore, approval of these changes will not create the possibility of a new or different kind of accident from any previously analyzed.

c. Involve a significant reduction in a margin of safety.

As previously stated, the coolant iodine activity limits have remained unchanged at operating levels equal to or greater than 80%

power. At operating levels less than 80% power, higher coolant iodine activity limits would be permitted than those previously allowed. While this could be considered as a relaxation to existing requirements, it is not considered a significant reduction in a margin of safety because these limits are only allowed at reduced thermal power conditions. The NRC has generically accepted these limits for Combustion Engineering plants in NUREG-0212, Revision 2.

Based on the above evaluation, this change does not involve a significant hazards consideration.

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