ML20065K579
| ML20065K579 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/09/1990 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20065K581 | List: |
| References | |
| TAC-77638, TAC-77639, TAC-77726, NUDOCS 9012030022 | |
| Download: ML20065K579 (2) | |
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SNppmgpyt PA 40774004 go Sg October 9, 1990 1
m,
'U.
S. Nuclear. Regulatory Commission Attn:
Document Control Dcsk
. Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NpF-73 Proposed Operating License Change Roquest No. d6 (TtC No. 77726)
' Gentlemen:
Encl'osed are:
1.
An ' application for. amendment to the above dictnoe to revise the Containment Otructural Integrity Survei..lar.ce Specification 4.6.1.6.1-to : add the wording contained in the Svendard Technical Specifications.
L 2.
Documents designated Attachments A, B and C which set forth the.
change-in the Technical Specifications, the safety analysis, including the no-significant hazards evaluation, and the typed-replacement _ Technical Specification pages.
On. October _
1,
- 1990, we submitted Proposed Operating License-Change
. Request No. 181/45 (TAC Nos. 77638 and 77639) and requested expedited action -due-to-the' exigent circumstances.that exist to support restart frem our-second refueling outage.
During a
conference call on-Friday, _ October.
5,
- 1990, we were advised that this proposed change i
could-not be ' approved-in time to support the scheduled entry into Mode
-4 for-Unit. No. - 2 following this refueling: ' outage.-
An-alternative plan was developed which -would support our refueling activities.
1
'h e. attached proposed Technical Specification Change is a result of at' conference call.
This. change is applicable to Unit No. 2 only 3
consists ;of the addition of the Standard Technical' Specification
,rding. to the existing surveillance requirements of.' specification l-4.6.1.6.1.
This additional wording is intended. to _ provide an-li alternate! means of-performing' inspections of the containment vessel surfaces (ie:- liner plate and concrete) prior to conducting the Type-1A.. containment;, leakage rate ' test to verify no apparent changes in
= appearance or other' abnormal: degradation.-
We request-that-.this proposed change be handled as an emergencyc V Technical Specification Change in accordance with 10 CFR l
D '50.91(a) (5).
Our present schedule for conducting our Type A-test.is M to begl'n' testing on October 26, 1990.
Based on the conference call, h we were advised that this proposed change would have-to be approved by the NRC prior to starting the Type A-test, therefore, it'is necessary-that the change-be handled as an emergency change.
The 1
-following represents-background information supporting this proposed change.
9012030022 901u09 gO/
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Chango Roquest No. 46 Page 2 i
l l
During the inspection of the containment liner, it was observed that a
number of containment liner test channel vent plugs were missing.
Our first indication of missing vent plugs occurred on approximately September 17,
- 1990, as we performed the required inspections which precede our Type A containment leakage rate test.
The existing Technical Specifications would require that we remove the test channels associated with the missing vent plugs.
The number of missing vent plugs has resulted in an estimated 1500 feet of test channel which would have to be removed in order to satisfy the Technical Specifications.
We have identified 25 uissing vent plugs, 13 of which are associated with test channels on the liner floor and covered with two feet of reinforced concrete.
It is more prudent from a
radiological perspective and from a technical perspective to justify leaving the test channel intact and request a change to the Technical Specifications.
The information presented in the attachments provides our technical basis for leaving the test channels installed.
This Type A
test is the first performed following commercial operation and as such is the first scheduled 4
containment liner inspection since pre-op testing where we could have discovered the missing vent plugs.
Several activities have been completed to assess the containment liner condition under the test channels where the vent plugs were identified as missing.
A borascope inspection was performed to examine the liner weld at several locations.
Additionally, water samples were extracted from two channels found to be holding water.
Chemical analyses of these samples have provided confidence that the actual corrosion rate within the test channels has not exceeded that predicted.
Further information regarding these inspections may be found in Attachment B.
It is requested that the NRC approve this proposed change by October 26, 1990 to support our current outage schedule for conducting our Type A containment leak rate test.
Sincerely, J.
D. Sieber Vice President Nuclear Group cc:
Mr. J.
Beall, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr. A. W.
DeAgazio, Project Manager Mr. R.
Saunders (VEPCO)