ML20034F185
| ML20034F185 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/19/1993 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, TAC-M69428, NUDOCS 9303020368 | |
| Download: ML20034F185 (1) | |
Text
.
08
- 0B Shrppmgport, PA 15077-0004 An
i February 19, 1993 JOHN D. SIEBER (412) 393 4255 l
Senior Wce President and Fax (412) 643-8069 l
Quef Nuclear Officer Nuclear Power Dmsson U.
S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Subject:
Beaver Valley Power Station, Unit No.
1.
Docket No. 50-334, License No. DPR-66 l
Supplement 1 to Generic Letter 87-02 on SQUG Resolution of USI A-46 (TACf,69428)
By letter dated September 22,
- 1992, Duquesne Light Company i
provided a
commitment to the SQUG Generic Implementation Procedure
[
(GIP) in response to Supplement 1
On i
November 25, 1992, the NPC transmitted the Safety Evaluation related to our response and stated the NRC's interpretation.
This letter responds to the NRC's interpretation and clarifies our previous
}
response.
The NRC interpreted our response as a commitment to the entire i
GIP-2, including both the SQUG commitments and the implementation i
guidance.
Duquesne Light Company concurs with the NRC's i
interpretation.
We note in the NRC's January 20, 1993 response to the SQUG that "The staff acknowledges that such a commitment does not preclude a
licensee from deviating from the GIP-2 implementation guidance if any such deviations are in accordance with GIP-2, Part I, Section 1.3, as supplemented by the staff's SSER No.
2."
i Additionally, Duquesne Light Company will follow the August 21,
- 1992, SQUG letter for implementing GIP-2 and will also reference the l
NRC staff's October 2, 1992, response to the SQUG letter.
j We also note that Duquesne Light Company does not intend to change the Beaver Valley Power Station, Unit No. 1 licensing basis to reflect a
commitment to the USI A-46 methodology prior to reccipt of the NRC staff's plant specific safety evaluation.
Should you have any questions regarding this submittal, please contact Ed Coholich at (412) 393-5224.
l I
Sincerely, j
01015L
/
l
~
u 7
J.
D.
Sieber 7 y..~ ~ '
cc:
Mr.
L. W. Rossbach, Sr. Resident In_pector Mr.
T. T. Martin, NRC Region I Administrator h h fh Mr.
G.
E.
Edison, Pro],ect Manager THE MMR i
Mr. M. L. Bowling (VEPCO)
{
- d, [ j g; 9303020368 930219 J j')^
PDR ADOCK 05000334 P
PDR i
.i t