ML20082J910
| ML20082J910 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/07/1995 |
| From: | George Thomas DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-U00812, TAC-U812, NUDOCS 9504180497 | |
| Download: ML20082J910 (5) | |
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o Beaver Valley Power Station Sh pn rt PA 15077 0004 (412) 643-8069 FAX GEORG'E S. THOMAS
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April 7, ' 1994 a ervic Nuclear Power Division U. S.' Nuclear Regulatory Commission 1
' Attn:
Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66
.i BV-2 Docket No. 50-412, License No. NPF-73 Quality Assurance Program nams.ription Change
Reference:
Letter from NRC to Duquesne Light Company dated June 8, 1994, 10 CFR 50.54 Quality Assurance Program Change Review; NRC:QA94-12, TAC U00812 In accordance with - 10 CFR 50.54 (a) (3), this letter forwards, ' for NRC
- approval, a
proposed change to the quality assurance program description included in the Safety Analysis Report._
The change includes wording submitted in a previous quality assurance program
]
change request dated April 8,
- 1994, and adds a requirement which j
addresses staff concerns presented in the_above referenced letter.
The additional requirement states that biennial audits of operating organizations include a
sample of each organization's procedures.
This procedure audit provides additional assurance that existing programmatic controls are resulting in the timely revision of procedures when operating experience or other deficiencies are-identified by procedure users.
Attachment 1
provides draft safety analysis report pages incorporating the proposed changes.
The reason for the change and the basis for concluding that the revised program incorporating'this change continues to satisfy the criteria of 10 CFR 50, Appendix B, were presented in the quality assurance program change request dated
-April 8, 1994.
If you have any questions or concerns related to these proposed
- changes, please contact Mr. Nelson R. Tonet, Manager, Nuclear Safety, at (412) 393-5210.
Sinceraly, Geo ge S. Thomas cc:
Mr. L. W. Rossbach, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr. D.
S. Brinkman, Sr. Project Manager 0
9504180497 950407
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PDR ADOCK 05000344 P
PDR a
l ATTACHMENT 1 Pcg3 1 cf 4 BVPS-1-UPDATED FSAR be required to determine the acceptability of the welds.
The l
sample size shall be 10 percent of the welds in the system or component.
If any of these weld samples are defective, that is, fail to pass bend tests as prescribed by ASME Code, l
Section IX, all remaining welds shall be sampled and all defective welds shall be removed and replaced."
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1.3.3.32 Use of IEEE STD-308-1971 " Criteria for Class lE Electric Systems for Nuclear Power Generating Stations" (Safety Guide 32) l l
l Class lE electric systems, to the greatest extent possible, comply with Safety Guide 32.
Availability of offsite power is discussed in Appendix 1A.17.
The capacity of each battery charger supply is based on the l
largest combined demands of the various steady state loads and the charging capacity to restore the battery to the fully charged
- state, irrespective of the status of the plant during which these demands occur.
1.3.3.33 Quality Assurance Program Requirements (Operation) l (Safety Guide 33) 1 BVPS-1 has formed a Quality Assurance Department. This department is responsible for the administration of the operational quality i
l assurance program.
The BVPS-1 Quality Assurance Manual has been revised to incorporate quality assurance for operations.
This prog complies with AEC Safety Guide 33.
ANSIN45.2andANSIN18.7ygg (previously ANS 3.2) requirements are referenced within Safety l
Guide 33.
1 BVPS-1 Quality Control is responsible for the preparation of the quality control procedures necessary to comply with Safety Guide 33.
1.3.4 Guidelines Used for the Duauesne Licht Comoany Operations l
Ouality Assurance Procram i
1.3.4.1 Regulatory Guides l
l REGULATORY GUIDE 1.33, NOVEMBER 3,
1972:
QUALITY ASSURANCE l
PROGRAM REQUIREMENTS (OPERATIONS)
The Duquesne Light Company Operations Quality Assurance Program requirements follow the guidance of Regulatory Guide 1.33, November 3,
1972 [ including referenced standards ANSI N45.2, 1971 l
and ANSI N18.7, 1972 (formerly ANS 3.2)].
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1.3-48 l
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ATTACHMENT 1 Paga 2 of 4 BVPS-1-UPDATED FSAR Appendix A
of Regulatory Guide 1.33, (Revision 2, February 1978),
is used as guidance to ensure minimum procedural coverage for plant activities.
The biennial review of safety related plant procedures described in ANSI N18.7 will be replaced by programmatic controls related to procedure review found in plant administrative procedures, and a maximum six year procedure review period.
Biennial audits of operating organizations will include a review of their procedures to provide additional assurance that existing programmatic controls are resulting ir. the timely revision of their procedures in response to operations experience deficiencies and procedure deficiencies identified by users.
l REGULATORY GUIDE 1.37, MARCH 16, 1973:
QUALITY ASSURANCE REQUIREMENTS FOR CLEANING OF FLUID SYSTEMS AND ASSOCIATED l
COMPONENTS OF WATER-COOLED NUCLEAR POWER PLANTS t
The Euquesne Light Company Operations Quality Assurance Program requirements follow the guidance of Regulatory Guide 1.37.
(
Procedures and/or specifications were developed prior to, and implemented concurrent with the start of the operations phase.
REGULATORY GUIDE 1.38, MARCH 16, 1973:
QUALITY ASSURANCE l
REQUIREMENTS FOR PACKAGING,
- SHIPPING, RECEIVING,
- STORAGE, AND l
HANDLING OF ITEMS FOR WATER-COOLED NUCLEAR POWER PLANTS I
The Duquesne Light Company Operations Quality Assurance Program requirements follow the guidance of Regulatory Guide 1.38.
Procedures and/or specifications were developed prior to, and l
implemented concurrent with the start of the operations phase.
REGULATORY GUIDE 1.39, MARCH 16, 1973:
HOUSEKEEPING REQUIREMENTS FOR WATER-COOLED NUCLEAR POWER PLANTS l
The Duquesne Light Company Operations Quality Assurance Program requirements follow the guidance of Regulatory Guide 1.39.
Procedures and/or specifications were developed prior to, and implemented concurrent with the start of the operations phase.
REGULATORY GUIDE 1.54, JUNE, 1973:
QUALITY ASSURANCE REQUIREMENTS FOR PROTECTIVE COATINGS APPLIED TO WATER-COOLED NUCLEAR POWER PLANTS The Duquesne Light Company Operations Quality Assurance Program requirements follow the guidance of Regulatory Guide 1.54.
Procedures and/or specifications were developed prior to, and implemented concurrent with the start of the operations phase.
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1.3-49
l ATTACHMENT 1 Pign 3-of 4 l
BVPS-2 UFSAR l
TABLE 1.8-1 (Cont)
Following the guidance of any of the preceding document revisions was based primarily on the revision in effect on.the date of the last specification revision wherein the regulatory. guide was invoked.
Since each revision of the regulatory guide is less restrictive than the foregoing, following the guidance of. any of the revisions is considered acceptable.
RG No. 1.32, Rev. 2 UFSAR Reference Sections 7.5, 8.1.5, 8.2, 8.3.1, 8.3.2, 7.5.2.3.1.3 CRITERIA FOR SAFETY-RELATED ELECTRIC POWER SYSTEMS FOR NUCLEAR ~ POWER PLANTS (FEBRUARY 1977)
I f
The design of the safety-related electric power systems for Beaver l
Valley Power Station - Unit 2 (BVPS-2) follows IEEE Standard t
l 308-1974, and the guidance of Regulatory Guide 1.32, with the following clarifications:
i Two immediate access offsite power circuits are provided.
Each circuit is designed to be immediately available following a loss of onsite alternating current power supplies so that sufficient power capacity remains for an orderly shutdown.and to supply all train related engineered safety feature loads:
l Each battery charger that supplies Class IE 125 V de systems is
(
designed with full capacity and capability to supply the largest l
combined demands of the various steady state loads. while l
simultaneously providing sufficient power for adequate charging capacity to restore the battery.from the design minimum charged state to the charged state irrespective of the BVPS-2 status during which these demands occur.
For test methods, procedures, and intervals for all Class IE battery performance discharge and service tests, refer to the position on Regulatory Guide 1.129.
RG No. 1.33, Rev. 2 l
UFSAR Reference Sections 13.4, 13.5, 17.2 OUALITY AJSURANCE PROGRAM REOUIREMENTS (OPERATION) (FEBRUARY 1978)
The Quality Assurance Program for the operating-phase of Beaver valley Power Station - Unit 2 will follow the guidance of this regulatory guide with the following clarification of Paragraph C.2, l
and alternative to the biennial review described in ANSI N18.7.
l' Paraaraoh C.2 l
The applicability of the referenced regulatory guides (1.8, 1.17,-
1.28, 1.30, 1.37, 1.38, 1.39, 1.54, 1.58, 1.64, 1.74, 1.88, 1.94, 14 of 80 I
l ATTACHMENT 1 Pngs 4 of 4 i
BVPS-2 UFSAR i
1 TABLE 1.8-1 (Cont) l 1.116, and 1.123) is as stated in the respective positions on l
these regulatory guides.
Alternative To Biennial Review The biennial review of safety related plant procedures described in ANSI N18.7 will be replaced by programmatic controle related-to procedure review found in plant administrative procedures, l
and a maximum six year procedure review period.
Biennial audits of operating organizations will include a review of their procedures to provide additional assurance that existing programmatic controls are resulting in the timely revision of their procedures in response to operations experience deficiencies and procedure deficiencies identified by users.
l RG No. 1.34, Rev. O I
UFSAR Reference Section 5.2.3 CONTROL OF ELECTROSLAG WELD PROPERTIES (DECEMBER 28, 1972)
The guidance provided by this regulatory guide regarding control of electroslag weld properties was followed for fabrication of applicable components for Beaver Valley Power Station - Unit 2.
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RG No. 1.35. Rev. 2 INSERVICE INSPECTION OF UNGROUTED TENDONS IN PRESTRESSED CONCRETE CONTAINMENT STRUCTURES (JANUARY 1976)
This regulatory guide is not applicable to Beaver Valley Power Station - Unit 2.
RG No. 1.36. Rev. O UFSAR Reference Sections 5.2.3, 6.1.1 NONMETALLIC THERMAL INSULATION FOR AUSTENITIC STAINLESS STEEL (FEBRUARY 23, 1973)
Nonmetallic thermal insulation for austenitic stainless steel used at Beaver Valley Power Station - Unit 2 meets the intent of this regulatory guide.
As an alternative to controlled packaging and l
shipping described in Paragraph C.1, receipt inspection and tests are j
required by specification.
This testing and inspection consists of l
visual inspection for physical or water damage to all cartons.
Damaged cartons are segregated.
Potentially contaminated insulation j
is not accepted, unless randomly selected samples from each carton are, shown to be acceptable after being resubjected to the production test outlined in this regulatory guide.
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l 15 of 80 l
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