ML20052B391
| ML20052B391 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs |
| Issue date: | 04/16/1982 |
| From: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20052B378 | List: |
| References | |
| 50-317-82-05, 50-317-82-5, 50-318-82-05, 50-318-82-5, NUDOCS 8204300367 | |
| Download: ML20052B391 (3) | |
Text
I APPENDIX A NOTICE OF VIOLATION Baltimore Gas and Electric Company Docket / License: 50-317/DPR-53 Calvert Cliffs Units 1 and 2 50-318/DPR-69 During inspection from March 2,1982 - April 13,1982 and in accordance with the NRC Enforcement Policy,10CF2 Appendix C (47FR9987, March 9,1982), the following violations were identified.
A.1 10CFR20.203(b) requires conspicuous posting of each radiation area with a sign or signs bearing the radiation caution symbol and the words " Caution" and " Radiation Area." 10CFR20.202(b)(2)definesaradiationareaasan accessible area where a major portion of the body could receive more than l
5 millirem in any hour or more than 100 millirem in any 5 consecutive l
days.
Contrary to the above, on March 25, 1982 the Unit 2 Refueling Water Tank Room was not posted as a radiation area when an inspector-performed survey measured gencral area radiation' levels.of 4 millirem per hour, I
representing about 160 millir mi.in a nomal 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, 5 day week.
This 'is a Severity Level 'V Violation ~ (Supplement -IV) a'pplicable to DPR-69.
A.2 10CFR50 Appendix B Criterion VI, requires control of issue of documents, including drawings and changes, to assure their use where activities are perfomed. The Operations Quality Assurance Program, Section 1C.6 re-vised October 1,1976, requires organizations issuing drawings to establish controls that assure approved changes are promptly incorporated. Calvert Cliffs Instruction CCI-131B, Drawing Control, revised July 14, 1981, contains detailed instructions for processing of Drawing Change Notices (DCN's) on receipt, including incorporation into catalogs at user locations and entering the number of the DCN on the Attachment Stamp of the appropriate controlled drawing.
Contrary to the above, the onsite controlled copy of Drawing 87-306-E, Sheet 14, Electrical Wiring Diagram Panel 2006 (Reactor Control System Control Board) was not annotated with the following changes by March 30, 1982.
DCN, Date Received
' Description' M-346-ll6-2018,11/21/77 FCR 76-1054, Power Operated Relief Valve Dual Set Point Capability M-346-ll6-2026, 05/06/80 FCR 79-1043, New Teminals and Wiring for Subcooled Margin Monitor
- 367, 00 '
82043 0FFICIAL RECORD COPY
(
I Baltimore Gas and Electric Company 2
DCN, Date' Received Description M-346-116-2032,12/16/80 FCR 80-1015, Annunciator Relocation 13374A15SH14-1, 08/06/80 FCR 79-1054, Reactor Coolant Vent System 13374A15SH14-3,01/07/81 FCR 79-1045, Technical Support Center Installation 13374A15SH14-4,01/15/81 FCR 79-1054, Reactor Coolant Vent System 13374A15SH14-5,01/23/81 FCR 79-1045, Technical Support Center Installation This is a Severity Level IV Violation (Supplement I) applicable to DPR-69.
l A.3 10CFR50.59(a)(1) pennits a licensee to change a facility as described in the Safety Analysis Report, without prior Comission approval, only when a change in technical specifications or an unreviewed safety question is not involved.
10CFR50.59(b) requires that records of such changes be main-tained including written safety evaluations providing the bases for'the -
determination that.they do not.iny'olve an unreviewed safety question.
Contrary to the above, on March 26, 1982 the ' inspector detennined that the'below listed motor-operated valves and piping had been added to systems described in the Units 1 and 2 Final Safety Analysis Report without prior safety evaluation to determine if an unreviewed safety question was involved.
Motor-operated valves I-SI-399 and 2-SI-399 were added to existing Unit 1 and 2 cross-connection piping between the Low Pressure Safety Injection and Shutdown Cooling Systems.
Motor-operated valves I-CVC-269 and 2-CVC-269 and associated piping provided a bypass path around existing manual valve CVC-269 and check valve CVC 270 in the Unit 1 and 2 Chemical and Volume Control Systems This is a Severity Level IV Violation (Supplement I) applicable to DPR-53 and DPR-69.
Pursuant to 10CFR2.201, Baltimore Gas and Electric Company is hereby required to submit to this office within 30 days of the date of this Notice, a written reply OFFICIAL RECORD COPY
Baltimore Gas and Electric Company 3
including (1) the corrective steps taken and the results achieved, (2) corrective steps to be taken to avoid further violations, and (3) the date when full compliance will be achieved.
Where good cause is shown, consideration will be given to extending the response time.
[b1Wg Dated original signed By:
P.ichard W. Starostecki, Director Division of Project and Resident Programs Ii E
- i.I1 l
r OFFICIAL RECORD CCPT L