ML20094F936: Difference between revisions

From kanterella
Jump to navigation Jump to search
StriderTol Bot insert
 
StriderTol Bot change
 
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:..  -.          -      -    ,    .        .        .        -    - . -      .        - ..
{{#Wiki_filter:..
  <~
<~
* VIRGINIA ELucTHIC AND POWER COMPANY It!CIIMOND,YIRGINIA 20261
VIRGINIA ELucTHIC AND POWER COMPANY It!CIIMOND,YIRGINIA 20261 November 3,1995 United States Nuclear Regulatory Commission Serial No.
              -                              November 3,1995 United States Nuclear Regulatory Commission                 Serial No.       95-555 Attention: Document Control Desk                             NAPS /JHUMAE R4 Washington, D. C. 20555                                     Docket Nos.       50-338 50-339 License Nos.     NPF-4 NPF-7 Gentlemen:
95-555 Attention: Document Control Desk NAPS /JHUMAE R4 Washington, D. C. 20555 Docket Nos.
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NOS.1 AND_2 CHANGE IN COMMITMENT FOR ULTRASS: .,
50-338 50-339 License Nos.
TESTING OF EQUIPMENT AND ESCAPE HATCH SEALS On February 27,1990, in an enforcement conference, Virginia Electric and Power Company presented the circumstances of a containment equipment hatch emergency escape lock door leakage event. During the conference, the requirements of Technical Specification 3.6.1.1, Containment Integrity, were discussed. The surveillance demonstrating the operability of the equipment and escape hatches once per 31 days by ultrasonically testing the seal, was incorrectly attributed as a Technical Specification requirement. Surveillance Requirement 4.6.1.1 does not specifically require ultrasonic testing. Ultrasonic testing of the seals has continued to be performed in addition to the surveillance requirements.
NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NOS.1 AND_2 CHANGE IN COMMITMENT FOR ULTRASS:.,
TESTING OF EQUIPMENT AND ESCAPE HATCH SEALS On February 27,1990, in an enforcement conference, Virginia Electric and Power Company presented the circumstances of a containment equipment hatch emergency escape lock door leakage event.
During the conference, the requirements of Technical Specification 3.6.1.1, Containment Integrity, were discussed. The surveillance demonstrating the operability of the equipment and escape hatches once per 31 days by ultrasonically testing the seal, was incorrectly attributed as a Technical Specification requirement. Surveillance Requirement 4.6.1.1 does not specifically require ultrasonic testing. Ultrasonic testing of the seals has continued to be performed in addition to the surveillance requirements.
The Technical Specifications currently require pressure testing of the containment
The Technical Specifications currently require pressure testing of the containment
        . equipment hatch and emergency escape lock doors. Pressure testing has been effective in maintaining containment equipment hatch and emergency escape lock door integrity. Ultrasonic testing of the containment equipment hatch and emergency escape lock doors has been performed to confirm the results of pressure testing. It has now been determined that ultrasonic testing is not an effective method for identifying seal leakage. Furthermore, ultrasonic testing results in additional personnel radiation exposure without commensurate benefit.
. equipment hatch and emergency escape lock doors. Pressure testing has been effective in maintaining containment equipment hatch and emergency escape lock door integrity. Ultrasonic testing of the containment equipment hatch and emergency escape lock doors has been performed to confirm the results of pressure testing. It has now been determined that ultrasonic testing is not an effective method for identifying seal leakage.
Furthermore, ultrasonic testing results in additional personnel radiation exposure without commensurate benefit.
Therefore, based on the above discussion, our previous commitment to perform ultrasonic testing of the containment equipment hatch and emergency escape lock doors at least once per 31 days is being discontinued. Containment integrity will be verified in accordance with the Surveillance Requirements of Technical Specification 3.6.1.1 and 3.6.1.3.
Therefore, based on the above discussion, our previous commitment to perform ultrasonic testing of the containment equipment hatch and emergency escape lock doors at least once per 31 days is being discontinued. Containment integrity will be verified in accordance with the Surveillance Requirements of Technical Specification 3.6.1.1 and 3.6.1.3.
If you have any questions, please contact us.
If you have any questions, please contact us.
Very truly yours, 7
Very truly yours, 7
James P. O'Hanlon Senior Vice President - Nuclear 9o\
James P. O'Hanlon Senior Vice President - Nuclear 9o\\
9511090150 951103                                         ]
9511090150 951103
PDR       ADOCK 05000338                                       \0
]
,          O                    PDR l
PDR ADOCK 05000338
\\0 O
PDR l


cc: , U.$. Nuclear Regulatory Commission Region ll                                                                                                                       t 101 Marietta Street, N.W.
, U.$. Nuclear Regulatory Commission cc:
Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRC Senior Resident Inspector                                                                                                   ;
Region ll t
i North Anna Power Station
101 Marietta Street, N.W.
_ , _ .      __.}}
Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRC Senior Resident Inspector i
North Anna Power Station
.}}

Latest revision as of 09:36, 13 December 2024

Submits Change in Commitment for Ultrasonic Testing of Equipment & Escape Hatch Seals.Containment Integrity Will Be Verified,Per Surveillance TS 3.6.1.1 & 3.6.1.3
ML20094F936
Person / Time
Site: North Anna  
Issue date: 11/03/1995
From: O Hanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-555, NUDOCS 9511090150
Download: ML20094F936 (2)


Text

..

<~

VIRGINIA ELucTHIC AND POWER COMPANY It!CIIMOND,YIRGINIA 20261 November 3,1995 United States Nuclear Regulatory Commission Serial No.95-555 Attention: Document Control Desk NAPS /JHUMAE R4 Washington, D. C. 20555 Docket Nos.

50-338 50-339 License Nos.

NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NOS.1 AND_2 CHANGE IN COMMITMENT FOR ULTRASS:.,

TESTING OF EQUIPMENT AND ESCAPE HATCH SEALS On February 27,1990, in an enforcement conference, Virginia Electric and Power Company presented the circumstances of a containment equipment hatch emergency escape lock door leakage event.

During the conference, the requirements of Technical Specification 3.6.1.1, Containment Integrity, were discussed. The surveillance demonstrating the operability of the equipment and escape hatches once per 31 days by ultrasonically testing the seal, was incorrectly attributed as a Technical Specification requirement. Surveillance Requirement 4.6.1.1 does not specifically require ultrasonic testing. Ultrasonic testing of the seals has continued to be performed in addition to the surveillance requirements.

The Technical Specifications currently require pressure testing of the containment

. equipment hatch and emergency escape lock doors. Pressure testing has been effective in maintaining containment equipment hatch and emergency escape lock door integrity. Ultrasonic testing of the containment equipment hatch and emergency escape lock doors has been performed to confirm the results of pressure testing. It has now been determined that ultrasonic testing is not an effective method for identifying seal leakage.

Furthermore, ultrasonic testing results in additional personnel radiation exposure without commensurate benefit.

Therefore, based on the above discussion, our previous commitment to perform ultrasonic testing of the containment equipment hatch and emergency escape lock doors at least once per 31 days is being discontinued. Containment integrity will be verified in accordance with the Surveillance Requirements of Technical Specification 3.6.1.1 and 3.6.1.3.

If you have any questions, please contact us.

Very truly yours, 7

James P. O'Hanlon Senior Vice President - Nuclear 9o\\

9511090150 951103

]

PDR ADOCK 05000338

\\0 O

PDR l

, U.$. Nuclear Regulatory Commission cc:

Region ll t

101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRC Senior Resident Inspector i

North Anna Power Station

.