ML19324B385
| ML19324B385 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 10/24/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19324B381 | List: |
| References | |
| NUDOCS 8911060185 | |
| Download: ML19324B385 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATICN RELATED TO AMENDMENT NOS.124, 35, AND 144 I
TO FACILITY OPERATING LICENSE NOS. DPR-61. DPR-21 AND DPR-65 CONNECTICUT YANKEE ATOMIC POWER COMPANY AND NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.
HADDAM NECK PLANT AND MILLSTONE NLt. LEAR POWER STATION, UNIT NO3. 1 AND 2 DOCKET.NOS. 50-?13, 50-245 AND 50-336
1.0 INTRODUCTION
By application for license amendments dated April 25, 1989, supplemented by letter June 26,1989,' Connecticut Yankee Atomic Power Company and Northeast Nuclear Energy Company (the licensees) requested changes to the Technical Specifications (TS) for the Haddam Neck Plant and Millstone Unit Nos. I and 2.
The proposed change to the TS would revise the TS Sections 6.12, "High Radiation Area," for.Haddam Neck and Millstone Unit'2
>1 ants and TS Section 6.13. "High Radiation Area " for Millstone Unit 1 plant >y (1) defining the dose rate as measured at 45 cm (18 inches) from the source, (2) increasing the Radiation Work Permit requirements for entry'into locked High Radiation areas with dose rates greater than the 1000 mR/h by requiring maximum stay time limits or continuous surveillance, (3) allowing an alternative to enclosing and locking large areas with dose rates greater than 1000 mR/h and in which an enclosure cannot be reasonably constructed and (4) defining locked High Radiation areas as those with dose rates greater than 1000 mR/h at 18 inches from the radiation source.
2.0 DISCUSSION-The current TS do not specify the distance from the source in determining high radiation areas. The current methodology to determine dose rates for high radiation areas (areas of 100 mR/h to 1000 mR/h and locked high radiation areas of greater than 1000 mR/h) at the Haddam Neck Plant and Millstone Unit Nos.1 ol' and 2 is for measuring dose 18 inches from the source. This is consistent with the Westinghouse Standard Technical Specifications that are implemented at Millstone Unit No. 3.
Thus, the proposed change would bring the TS in conformity L'
with what is currently in practice at all of the licensees' four nuclear plants and would reduce the possibility of overexposure.
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The proposed cnange increases the Radiation Work Permit requirements for entry L
into locked high radiation areas with radiation levels of greater than 1000 mR/H l
by requiring maximum stay time limits or continuous surveillance.
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For individual high radiation areas with radiation levels of greater than 1,000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, the proposed change would require that individual area to be barricaded, conspicuously posted, and a fleshing light be activated as a warning device.
3.0 EVALUATION 1
The staff has reviewed the licensee's proposed changes to the TS and finds that: (1) the changes are consistent with the Standard TS implemented at Millstone Unit 3, (previously approved Westinghouse 2)thespecificationofan18 inch distance for measuring dose is appropriate and is an enhancement to the radiological control program, (3) the change in Radiation Work Permit requiring i
a maximum stay time limit is appropriate and is consistent with the goals of ALARA, and (4) the change allowing an alternate to enclosing and locking large t
l' areas with dose rates greater than 1000 mR/hr and in which an enclosure cannot reasonably be constructed is appropriate and is responsive to the concerns of NRC Information Notice 88-79. Therefore, the staff concludes that the TS changes L
requested by the licensees are acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
I These amendments change administrative procedures and requirements. Accordingly, l
L the amendments meet the eligibility criteria for categorical exclusion set i
forth in 10 CFR 651.22(c)(10). Pursuant to 10 CFR 551.22(b), no environmental I
impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safet of the public will not be l
endangered by operation in the proposed manner, (y) such activities will be 2
I conducted in compliance with the Comission's regulations, and (3) the issuance 1
of the amendments will not be inimical to the comon defense and security or to l
the health and safety of the public.
Dated: October 24, 1989 Principal Contributor:
G. S. Vissing l
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