ML20235T691

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Safety Evaluation Supporting Util Request for Exemption from GDC-4 for Facility.Util Occupational Dose Saving Estimate for Plant Personnel of Approx 1,400 Person Rem Is Reasonable
ML20235T691
Person / Time
Site: Seabrook, 05000000
Issue date: 02/22/1985
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235T530 List: ... further results
References
FOIA-87-51, RTR-NUREG-0800, RTR-NUREG-800, RTR-REGGD-08.008, RTR-REGGD-8.008 NUDOCS 8707220238
Download: ML20235T691 (3)


Text

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.r INPUT BY THE RADIOLOGICAL ASSESSMENT BRANCH FOR THE SAFETY EVALUATION REPORT FOR SEABROOK REQUEST FOR AN EXEMPTIOh TO GDC-4 Seabrook Station Unit Nos. 1 & 2 .

Public Service of New Hampshire Docket Nos. 50-443 and 50-444 ,

i The staff has reviewed the occupational radiation protection aspects of the Public Service of New Hampshire's request for an exerption to GDC-4 for I

the Seabrook Station Units 1 & 2. The acceptance criteria used in the j evaluation were those stated in Section 12 of NUREG-0800, (SRP) and Regulatory Guide 8.8, "Information Relevant To Ensuring That Occupational Radiation Exposures At Nuclear Power Stations Will Be As Low As Is J Reasonably Achievable." The applicant, as part of the justification for the exemption to GDC-4, has estimated an occupational dose saving for i plant personnel of approximately 1400 person-rem for both units over. their operating lifetime. This occupational dose estimate is based on a break-down of occupational dose saving during inservice inspections and main-tenance procedures in and around the Reactor Coolant System. The staff review of the applicant's analysis shows it to be a reasonable estimate of dose saving. Therefore, from the perspective of radiation exposure and-ALARA considerations, the staff finds the applicant's request acceptable.

8707220238 870717 PDR FDIA GDRENB7-51 PDR

FJ3IOLOGICAL ASSESSMENT BRANCH - SALP INPUT I

PLANT: Seabrook 5:ation Unit Nos.1 & 2 A. Functional Areas: Licensing Activities 1 I

1. Managemer,: involvement in assuring quality.

The appli: ant's submittal describing potential occupational dose savings was more than the required minimum necessary to evaluate the exemp; ion request. Management involvement was average.

Rating: 2

2. Approach to resolution of technical issues from a safety standpoint.

The appli: ant demonstrated that ALARA and radiation safety aspects of the propcsed change were considered. No additional technical infor-mation was required by RAB, indicating the applicant's approach to resolutice of technical issues was significantly better than average.

Rating:  ;

3. Response :o NRC initiatives The appli: ant's submittal was based on information supplied by the NRC and t*e ALARA data were complete. The applicant's response was significa tly better than average.

Rating: 1 l

4. Staffing (including management). ,

1 No information j I

Rating. i

5. Reporting an analysis of reportable events i

N/A 1

l I

..O

6. Training and qualification effectiveness j N/A )

Rating:

7. Overall Rating for Licensing Activity Functional Area: 1 j B. Other Functier.al Areas (e.g., radiological controls, refueling) 1.

Rating:

2.

Rating:

1

1 1