ML20137U526: Difference between revisions

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ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company                                     Docket Nos. 50-270, 50-287 Oconee Nuclear Station                                 License Nos. DPR 47, DPR 55 The following violations were identified during an inspection conducted on December 10, 1985 - January 13, 1986. The Severity Levels were assigned in accordance with the NRC Enforcement Policy (10CFR Part 2, Appendix C).
ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-270, 50-287 Oconee Nuclear Station License Nos. DPR 47, DPR 55 The following violations were identified during an inspection conducted on December 10, 1985 - January 13, 1986.
: 1.     Technical Specification (TS) 3.1.6.2 requires the licensee to shut down the reactor within 24 hours of detection of any unidentified reactor coolant leakage which exceeds 1 gallon per minute (gpm), excl'oding normal evapora-tive losses.
The Severity Levels were assigned in accordance with the NRC Enforcement Policy (10CFR Part 2, Appendix C).
Contrary to there requirements, on Friday, December 13, 1985 upon detection of unit 2 reactor coolant leakage in excess of 1 gpm, the leakage was not subsequently identified or determined to be less than 1 gpm.       Prior to shutdown, unidentified leakage rate calculations ranged up to 1.65 gpm.
1.
While the licensee made every attempt to identify the leakage, a period of approximately 40 hours elapsed from the time of detection until the reactor was shut down.                                            .
Technical Specification (TS) 3.1.6.2 requires the licensee to shut down the reactor within 24 hours of detection of any unidentified reactor coolant leakage which exceeds 1 gallon per minute (gpm), excl'oding normal evapora-tive losses.
This violation applies to Unit 2 only.                   ],
Contrary to there requirements, on Friday, December 13, 1985 upon detection of unit 2 reactor coolant leakage in excess of 1 gpm, the leakage was not subsequently identified or determined to be less than 1 gpm.
Prior to shutdown, unidentified leakage rate calculations ranged up to 1.65 gpm.
While the licensee made every attempt to identify the leakage, a period of approximately 40 hours elapsed from the time of detection until the reactor was shut down.
This violation applies to Unit 2 only.
],
This is a Severity Level IV violation (Supplement 1).
This is a Severity Level IV violation (Supplement 1).
: 2.       Technical Specification 6.4.1 states that the station will be operated and maintained according to approved procedures. Tne Oconee Project Services Manual, Section 4.4, Exempt Changes, paragraph 3.5, requires that although the work described in an exempt change may proceed following verbal approval by Design Engineering, the system shall not be returned td service until the associated Variation Notice, which provides details of the change, is
2.
!            resolved by Design Engineering.
Technical Specification 6.4.1 states that the station will be operated and maintained according to approved procedures.
!.          Contraryito the above requirements, on October 6,1985, after receipt of
Tne Oconee Project Services Manual, Section 4.4, Exempt Changes, paragraph 3.5, requires that although the work described in an exempt change may proceed following verbal approval by Design Engineering, the system shall not be returned td service until the associated Variation Notice, which provides details of the change, is resolved by Design Engineering.
!            verbal approval, an exempt change was inplemented on a reactor coolant l           system sample line and the system returned to service prior to approval of i           the variation notice. Subsequently, the variation notice w'as' rejected by l           Design'En'gineering due to use of. materials with insufficient yell thickness.
Contraryi o the above requirements, on October 6,1985, after receipt of t
I         .This violation applies to Unit 3 only.
verbal approval, an exempt change was inplemented on a reactor coolant l
!              s l-This is a Severity Level IV violation (Supplement 1) i i Pursuant to 10 CFR 2.201, you are required to submit to this office within 30
system sample line and the system returned to service prior to approval of i
days of the date of this Notice, a written statement of expiar.ation in reply,.
the variation notice.
including: (1) admission or denial of the alleged violation; (2) the reasons s
Subsequently, the variation notice w'as' rejected by l
I                                                                             k I
Design'En'gineering due to use of. materials with insufficient yell thickness.
8602190232 860212 PDR     ADOCM 05000269 i
I
G                    PDR
.This violation applies to Unit 3 only.
;                                                                        ii
s l-This is a Severity Level IV violation (Supplement 1) i i
Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Notice, a written statement of expiar.ation in reply,.
including:
(1) admission or denial of the alleged violation; (2) the reasons s
I k
I 8602190232 860212 PDR ADOCM 05000269 G
PDR i
ii
[
[
: a.        .
 
  " Duke Powe'r Company                                 Docket Nes. 50-270, 50-287
a.
  ~0conee Nuclear Station                     2         License Nos. OPR 47, DPR 55 for the violation if admitted; (3) the corrective steps which have been taken and the results achieved;- (4) corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will be~ achieved.
" Duke Powe'r Company Docket Nes. 50-270, 50-287
~0conee Nuclear Station 2
License Nos. OPR 47, DPR 55 for the violation if admitted; (3) the corrective steps which have been taken and the results achieved;- (4) corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will be~ achieved.
Security or safeguards information should be submitted as an enclosure to facilitate witholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.
Security or safeguards information should be submitted as an enclosure to facilitate witholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.
Date:
II Date:
II
,}}
,}}

Latest revision as of 21:05, 11 December 2024

Notice of Violation from Insp on 851210-860113
ML20137U526
Person / Time
Site: Oconee  
Issue date: 02/12/1986
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20137U501 List:
References
50-270-85-41, 50-287-85-41, NUDOCS 8602190232
Download: ML20137U526 (2)


Text

'

ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-270, 50-287 Oconee Nuclear Station License Nos. DPR 47, DPR 55 The following violations were identified during an inspection conducted on December 10, 1985 - January 13, 1986.

The Severity Levels were assigned in accordance with the NRC Enforcement Policy (10CFR Part 2, Appendix C).

1.

Technical Specification (TS) 3.1.6.2 requires the licensee to shut down the reactor within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection of any unidentified reactor coolant leakage which exceeds 1 gallon per minute (gpm), excl'oding normal evapora-tive losses.

Contrary to there requirements, on Friday, December 13, 1985 upon detection of unit 2 reactor coolant leakage in excess of 1 gpm, the leakage was not subsequently identified or determined to be less than 1 gpm.

Prior to shutdown, unidentified leakage rate calculations ranged up to 1.65 gpm.

While the licensee made every attempt to identify the leakage, a period of approximately 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> elapsed from the time of detection until the reactor was shut down.

This violation applies to Unit 2 only.

],

This is a Severity Level IV violation (Supplement 1).

2.

Technical Specification 6.4.1 states that the station will be operated and maintained according to approved procedures.

Tne Oconee Project Services Manual, Section 4.4, Exempt Changes, paragraph 3.5, requires that although the work described in an exempt change may proceed following verbal approval by Design Engineering, the system shall not be returned td service until the associated Variation Notice, which provides details of the change, is resolved by Design Engineering.

Contraryi o the above requirements, on October 6,1985, after receipt of t

verbal approval, an exempt change was inplemented on a reactor coolant l

system sample line and the system returned to service prior to approval of i

the variation notice.

Subsequently, the variation notice w'as' rejected by l

Design'En'gineering due to use of. materials with insufficient yell thickness.

I

.This violation applies to Unit 3 only.

s l-This is a Severity Level IV violation (Supplement 1) i i

Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Notice, a written statement of expiar.ation in reply,.

including:

(1) admission or denial of the alleged violation; (2) the reasons s

I k

I 8602190232 860212 PDR ADOCM 05000269 G

PDR i

ii

[

a.

" Duke Powe'r Company Docket Nes. 50-270, 50-287

~0conee Nuclear Station 2

License Nos. OPR 47, DPR 55 for the violation if admitted; (3) the corrective steps which have been taken and the results achieved;- (4) corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will be~ achieved.

Security or safeguards information should be submitted as an enclosure to facilitate witholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.

II Date:

,