DCL-03-095, To License Amendment Request 03-05, Revision of Technical Specification (TS) 3.7.10, Control Room Ventilation System (Crvs). TS 3.7.12. Auxiliary Building Ventilation System (Abvs). TS 3.7.13
| ML032310383 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 08/08/2003 |
| From: | Oatley D Pacific Gas & Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| DCL-03-095 | |
| Download: ML032310383 (4) | |
Text
Pacific Gas and Electric Company David H. Oatley Diablo Canyon Power Plant Vice President and P0. Box 56 General Manager Avila Beach, CA 93424 August 8, 2003 805.545.4350 Fax: 805.545.4234 PG&E Letter DCL-03-095 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Supplement 1 to License Amendment Request 03-05 Revision of Technical Specification (TS) 3.7.10, "Control Room Ventilation System (CRVS)." TS 3.7.12. "Auxiliary Building Ventilation System (ABVS)." TS 3.7.13.
'Fuel Handling Building Ventilation System (FHBVS)." and TS 5.5.11, 'Ventilation Filter Testing Proaram (VFTP)."
Dear Commissioners and Staff:
On April 2, 2003, in PG&E letter DCL-03-034, PG&E submitted License Amendment Request (LAR) 03-05, "Revision of Technical Specification (TS)," 3.7.10, "Control Room Ventilation System (CRVS)," TS 3.7.12, "Auxiliary Building Ventilation System (ABVS)," TS 3.7.13, "Fuel Handling Building Ventilation System (FHBVS)," and TS 5.5.11, "Ventilation Filter Testing Program (VFTP)." The LAR, in part, proposed to revise TS 3.7.13 "Fuel Handling Building Ventilation System (FHBVS)" to add the word "recently" to qualify the irradiated fuel in the statement of applicability.
In support of that change, a new fuel handling accident analysis for the fuel storage area was performed. During a review of the LAR for impact on other potential changes to the TS, PG&E discovered that the LAR reflected preliminary analysis results, and had not been completely updated to reflect the final results of the analysis. The enclosed page 11 of DCL-03-034 has been revised to reflect the corrected dose numbers, and supersedes the same numbered page in Enclosure 1 of DCL-03-034.
Within the tables of this enclosed replacement page, the data have been revised as follows: The new calculated dose for the control room at 30 days was changed from 14 rem thyroid and 0.00466 rem whole body, to 22.3 rem thyroid and 0.00752 rem whole body. Although these doses are approximately 50 percent higher than those originally reported, they are still significantly lower than the general design criterion 19 dose limits of 30 rem to the thyroid and 5 rem to the whole body.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- South Texas Project
- Wolf Creek
Document Control Desk August 8, 2003 Page 2 PG&E Letter DCL-03-095 Also the new calculated dose at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the low population zone was revised from 4.27 rem to 0.112 rem total effective dose equivalent (TEDE). This revised dose is significantly less than the value previously provided in the subject LAR, and remains below the RG 1.183 acceptable dose guideline of 6.3 rem TEDE.
The corrections provided in this supplement do not change the conclusions of the safety evaluation and the no significant hazards determination previously transmitted in PG&E Letter DCL-03-034.
Sincerely, David H. Oatley Vice President and General Manager-Diablo Canyon dxs4 Enclosure cc:
Edgar Bailey, DHS Thomas P. Gwynn David L. Prouix Diablo Distribution cc/enc: Girija S. Shukla A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- South Texas Project
- WolfCreek
PG&E Letter DCL-03-095 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of PACIFIC GAS AND ELECTRIC COMPANY Diablo Canyon Power Plant Units 1 and 2
)
Docket No. 50-275 Facility Operating License No. DPR-80
) Docket No. 50-323
) Facility Operating License
) No. DPR-82 AFFIDAVIT David H. Oatley, of lawful age, first being duly sworn upon oath says that he is Vice President and General Manager - Diablo Canyon; that he has executed Supplement 1 to License Amendment Request 03-05 on behalf of said company with full power and authority to do so; that he is familiar with the content thereof; and that the facts stated therein are true and correct to the best of his knowledge, information, and belief.
David H. Oatley Vice President and General Manager-Diablo Canyon Subscribed and sworn to before me this 8 th day of August, 2003.
-Notary Public' if
/
County of San Lui bispo State of California CHUCK MACM Commission# 1397547 mNakir P -
c - Califtmic San Luis Obbix County My Comm. Expkrs Feb 1. 2007
Enclosure I PG&E letter DCL-03-034 control room dose consequences to assure that these remain below the 10 CFR 50, Appendix A, GDC 19, "Control Room" equivalent limits of 30 rem thyroid and beta skin, and 5 rem whole body.
The first of the two following tables shows the previous (current) exclusion area and offsite boundary dose consequences calculated for the FHA in the FHB. The values provided are from the FSAR Table 15.5-47. No previous values for the control room dose are given because there was no requirement for the control room dose to be determined for the previous FHA analysis in the FHB. The second table shows the new exclusion area, offsite boundary and control room dose consequences calculated for a FHA in the FHB at 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after a fuel assembly is removed from the reactor.
Current Doses (from FSAR Table 15.5.47)
Dose (rem)
Thyrid Whole Body Analysis Limit Analysis Limit 2-hr Exclusion Area Boundary 22.2 300 2.45 25 30 day Low Population Zone 0.923 300 0.102 25 Boundary I
_I New Doses Dose (rem)
Thy roid I
Whole Body I
Analysis I Limit Analysis [ Limit 30 day Control Room 22.3 1
30 0.00752 1
5 Fuel Handling Accident Analysis Methodoloav The new FHA in the FHB analysis was performed using the Bechtel standard computer program LOCADOSE, NE319, Release 6.0. This analysis provides the resultant radiological doses for the control room, exclusion area boundary, and low population zone. The LOCADOSE, NE319 program has been accepted for use in the industry and has been verified and validated.
LOCADOSE calculates radioactive material activities within regions in the plant, radioactive releases from regions of the plant, and doses and dose rates within regions of the plant and offsite locations. The solutions are obtained by solving a system of coupled differential radiation transport equations with boundary values. The 11