ML20235J450
| ML20235J450 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/08/1987 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-REGGD-01.088, RTR-REGGD-1.088 NUDOCS 8707150564 | |
| Download: ML20235J450 (5) | |
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$m lf Telephone (412) 393-6000 Nuclear Group P O. Box 4 Shippmgport, PA 150 4 0004 July 8, 1987 U.
S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412 10 CFR 50.54 Quality Assurance Program Description Change Gentlemen:
As a
result of the recent telephone conversation between members of the Duquesne Light Company and NRC staff it was determined that a commitment to the design and construction requirements of ANSI /ASME NQA-1 for QA record rooms is acceptable to the NRC.
Therefore, this l
letter supersedes our previous letter dated April 7,
1987 and l
forwards a
proposed change to the Beaver Valley Power Station Unit i
No.
1 (BVPS-1) Final Safety Analysis Report Quality Assurance Program description for your review and approval.
The proposed change also applies to the BVPS-2 Final Safety Analysis Report (FSAR) and involves a
change in our commitment to follow the guidance of Regulatory Guide 1.88
" Collection,
- Storage, and Maintenance or Nuclear Power Plant Quality Assurance Records".
Both BVPS-1 and BVPS-2 have committed in their respective FSARs to follow the guidance of Regulatory Guide 1.88.
Regulatory Guide 1.88 endorses ANSI N45.2.9-1974 which requires a minimum four hour fire rating for a
single Quality Assurance (QA) record storage 1
facility.
l In order to obtain a
variance from this four hour fire rating I
requirement, the BVPS-1 and BVPS-2 FSAR will be revised, as shown in f
Attachment A,
to state that BVPS follows the guidance of ANSI /ASME I
NQA-1
- 1983, supplement 175-1, Section 4.4 for the design and construction of a
single record storage facility.
Section 4.4 specifies a minimum 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> fire rating.
1 BVPS-1 and BVPS-2 currently utilize four QA records storage facilities.
Two of these facilities currently meet all the requirements of NQA-1 for the design and construction of a single records storage facility.
)
8707150564 070708 f 2 gd..
PDR ADDCK 05000334 P
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d Beaver Valley Power Station, Unit No. 1 and Unit No. 2 Docket No. 50-334 and 50-412, License No. DPR-66 10 CFR 50.54 Quality Assurance Program Description Change Page 2 The other two facilities do not meet all the design and construction requirements of NQA-1.
These two facilities will be modified to meet the design and construction requirements of NQA-1, or QA records stored in these facilities will be transferred to f
facilities that meet the design and construction requirements of 1
NQA-1 within one year (by July of 1988).
j l
Very truly yours,
. D. Sieber l
l Vice President, Nuclear l
1 Attachment cc: Mr. F.
I. Young, Resident Inspector U.
S. Nuclear Regulatory Commission l
Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission i
Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. Peter S. Tam U. S. Nuclear Regulatory Commission Project Directorate No. 2 l
Division of PWR Licensing - A l
Washington, DC 20555 l
- Mail Stop 316 l
Addressee only Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 l
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J
A T T A C H M'E N'T A
j l
The following will be added to the BVPS-1 Updated FSAR Page AA.2 and BVPS-2 FSAR Table 1.8-1 under Regulatory Guide 1~.88:
l with the exception that single Quality Assurance record storage facilities will be designed and constructed in accordance with the guidance of ANSI /ASME NQA-1-1983, Supplement 175-1, Section 4.4.
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1 J
1 c'
BVPS-1-UPDATED FSAR Rev. 1 -(1/ 83)
REGULATORY GUIDE 1.58, REVISION 1,
SEPTEMBER, 1980:
QUALIFICATION OF NUCLEAR POWER PLANT INSPECTION, EXAMINATION AND TESTING PERSONNEL i
The Duquesne Light Company Operations Quality Assurance Program -
I requirements follow the guidance of Regulatory Guide 1.58.
REGULATORY GUIDE 1.64:
QUALITY ASSURANCE REQUIREMENTS FOR DESIGN I
OF NUCLEAR POWER PLANTS 7
The Duquesne Light Company Operations - Quality - Assurance Program; requirements follow the guidance of Regulatory Guide'l.64.
j REGULATORY GUIDE 1.68, DRAFT 4, OCTOBER 2, 1973:
PRE-OPERATIONAL i
AND INITIAL START-UP TEST PROGRAM FOR WATER-COOLED POWER REACTORS The ' Duquesne Light Company Operations Quality. Assurance Program follows the guidance'of Regulatory Guide 1.68.
j REGULATORY GUIDE 1.70.11:
INFORMATION FOR SAFETY ANALYSIS i
REPORTS QUALITY ASSURANCE SAFETY OPERATIONS PHASE The Duquesne Light Company Operations Quality Assurance Program requirements follow the guidance of Regulatory Guide 1.70.11.
l REGULATORY GUIDE 1.88, AUGUST, 1974:
COLLECTION, STORAGE,- AND MAINTENANCE OF NUCLEAR POWER PLANT QUALITY ASSURANCE RECORDS The Duquesne Light Company Operations Quality Assurance Program follows the guidance of Regulatory Guide 1.88.
American National Standards Institute (ANSI) Standards i
N45.2.5:
DRAFT 3,
REVISION 1,
JANUARY 1974, ~" SUPPLEMENTARY QUALITY ASSURANCE REQUIREMENTS FOR ' INSTALLATION, INSPECTION AND TESTING OF STRUCTURAL CONCRETE AND STRUCTURAL STEEL DURING ' THE CONSTRUCTION PHASE OF NUCLEAR POWER PLANTS."
The Duquesne Light Company follows the guidance of ANSI N45.2.5, Draft 3, Revision 1, January 1974.
Procedures and/or specifications were developed prior to, and
. implemented concurrent with the start of the operations phase.
N45.2.8:
DRAFT 3,
REVISION 2,
SEPTEMBER 1973,. " SUPPLEMENTARY QUALITY ASSURANCE REQUIREMENTS FOR INSTALLATION, INSPECTION, AND TESTING OF MECHANICAL EQUIPMENT AND SYSTEMS FOR THE-CONSTRUCTION PHASE OF NUCLEAR POWER PLANTS".
The Duquesne Light Company follows the guidance of ANSI N45.2.8, Draft 3, Revision 2, September 1973.
Procedures and/or specifications were developed prior to, and implemented concurrent with the start of the operations phase.
AA.2
i BVPS-2 FSAR:
TABLE 1.8-1 (Cont)
RG No. 1.86, Rev. O FSAR Reference Section 5.8 (ER-OLS)
TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS (JUNE 1974)
The guidance of. this Regulatory Guide will be. followed when Unit 2 operating termination of the Beaver Valley Power Station license is desired.
RG No. 1.87. Rev. 1 GUIDANCE FOR CONSTRUCTION OF CLASS 1 COMPONENTS IN ELEVATED TEMPERATURE REACTORS (SUPPLEMENT TO ASME SECTION III CODE CASES 1592, 1593, 1594, 1595, AND 1596) (JUNE 1975)
This regulatory guide is not applicable to Beaver Valley Power Station - Unit 2.
RG No. 1.88, Rev. 2 FSAR Reference sections 9.5.1, 17.2 COLLECTION,
- STORAGE, AND MAINTENANCE OF NUCLEAR POWER PLANT QUALITY ASSURANCE RECORDS (OCTOBER 1976)
Beaver Valley Power Station - Unit 2 quality assurance records will be collected, stored, and maintained following the guidance of this regulatory guide.
L RG No. 1.89, Rev. 1 g
FSAR Reference Section 3.11 ENVIRONMENTAL QUALIFICATION OF CERTAIN ELECTRIC EQUIPMENT IMPORTANT TO SAFETi' FOR NUCLEAR POWER PLANTS (JUNE 1984)
BVPS-2 electric equipment important to safety is qualified to' meet or exceed the intent of IEEE Std. 323-1971 and Category II of NUREG 0588, Rev. 1.
For BVPS-2, this includes both safety-related and certain post-accident equipment.
When determined _possible by Duquesne Light Company, the qualification of this equipment will be upgraded to meet the standards set forth in Category I of NUREG-0588, Rev. 1.
In accordance with 10CFR50.49(k), BVPS-2 is not required to requalify electric equipment important to safety.(except replacement-equipment')
in-accordance with Regulatory Guide 1.89, Rev. 1.
Replacement electric equipment important_to safety will be qualified in accordance with the guidance provided in Paragraph C.6 of this regulatory guide. Qualification records for replacement electric equipment will meet the intent of Appendix E of this regulatory guide by meeting the applicable requirements of 10CFR50.49.
Amendment 12 45 of ' 80 June 1986