ML20078F529
| ML20078F529 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/25/1995 |
| From: | George Thomas DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.058, RTR-REGGD-1.058 NUDOCS 9502020141 | |
| Download: ML20078F529 (7) | |
Text
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Q Beaver Valley Power Station Stuppingport, PA 15077 4 )O4 (412) 393-5206 (412) 643-8069 FAX GEORGE S. THOMAS y'," y,*, P',"8'"'
January 25, 1995 D'
Nuclear Power Division U.
S.
Nuclear Regulatory Commission 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 BV-2 Docket No. 50-412, License No. NPF-73 Quality Assurance Program Description Change In accordance with 10 CFR 50.54 (a) (3) (li), this letter forwards for NRC approval proposed changes to the Beaver Valley Power Station Unit 1
and Unit 2 quality assurance program description included in each respective unit's safety analysis report.
The change would reduce commitments by adding an exception to our position on Regulatory Guide 1.58.
The exception would permit a 90 day extension for scheduled annual physical examinations when inspection, examination, and testing personnel are not available due to a
business trip, illness, vacation, or other schedule conflicts.
This proposed change would also revise the Unit 1 position on Regulatory Guide 1.58 to be consistent with the Unit 2 position.
The clarification for Regulatory Guide 1.58, Paragraph C.6 currently found in the Unit 2 UFSAR would be added to the Unit 1 UFSAR.
Attachment 1
further describes the proposed change, identifies the reason for the change, and provides the basis for concluding that the revised program incorporating these changes continues to satisfy the criteria of 10 CFR 50, Appendix B.
Attachment 2
presents the proposed wording for the Beaver Valley Power Station (BVPS)
Unit 1,
Updated Final Safety Analysis Report (UFSAR).
Attachment 3
presents the proposed wording for the BVPS Unit 2 UFSAR.
If you have any questions regarding this submittal, please contact Nelson R. Tonet, Manager, Nuclear Safety Department, at (412) 393-5210.
Sincerely N
0 ~,) (J 0.stv George S. Thomas g
cc:
Mr.
L. W.
Rossbach, Sr. Resident Inspector Mr.
T. T. Martin, NRC Region I Administrator Mr c-E.
Edison, Sr. Project Manager 9502020141 950125 80
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ATTACHMENT 1 BACKGROUND Regulatory Guide 1.58(1) describes a
method acceptable to the NRC staff for implementing 10 CPR 50, Appendix B requirements associated with the qualification of nuclear power plant inspection, examination, and g ting personnel. Regulatory Guide 1.58 refers to ANSI N45.2.6-1978 which states in Section 2.5 that:
"The responsible organization shall identify any special physical characteristics needed in the performance of each activity. Personnel j
requiring these characteristics shall have them verified by examination at intervals not to exceed one year."
CHANGE DESCRIPTION l
The exception would permit scheduling of physical examinations for inspection, examination, and testing personnel on an annual basis with a
maximum allowable extension of 90 days.
In addition, the i
clarification for Regulatory Guide 1.58 Paragraph C.6 currently found in the Unit 2 UFSAR would be added to the Unit 1 UFSAR.
REASON FOR THE CHANGE Scheduling conflicts occur when personnel are absent due to a
business
- trip, illness,
- vacation, or other reason on the date specified for their physical examination.
The proposed change would allow sufficient time to reschedule physical examinations within the j
maximum allowed examination interval when such conflicts occur.
The duration of the extension period (90 days) was chosen based on the generally accepted time interval extension for technical specification surveillances; i.e.,
a 25 percent extension of the normal time interval.
The change would also revise the Unit 1 UFSAR position on Regulatory Guide 1.58, Paragraph C.6, to be consistent with Unit 2 UFSAR wording and current organization practice.
BASIS FOR CONCLUDING TIIAT TIIE REVISED PROGRAM INCORPORATING THE CIIANGE CONTINUES TO SATISFY TIIE CRITERIA OF 10 CPR 50, APPENDIX B Appendix B
does not require that personnel be examined on an annual basis to verify that they possess special physical characteristics.
l The quality assurance program will continue to provide control over activities affecting the quality of structures,
- systens, and components, consistent with their importance to safety.
Activities affecting quality will continue to be accomplished under suitably controlled conditions.
Based on the
- above, it is concluded that the revised program will continue to satisfy the criteria of Appendix B.
ATTACHBODIT 1 NOTES l
(1) Regulatory Guide 1.58, Revision 1, Qualification of Nuclear Power Plant Inspection, Examination and Test Personnel 1
(September 1980).
(2) ANSI N45.2.6-1978 Qualification of Inspection, Examination and Testing Personnel For Nuclear Power Plants (Section 2.5, Physical).
I l
l i
l
ATTACHMENT 2 BVPS-1 UPDATED FSAR REGULATORY GUIDE 1.37, MARCH 16, 1973:
QUALITY ASSURANCE REQUIREMENTS FOR CLEANING OF FLUID SYSTEMS AND ASSOCIATED COMPONENTS OF WATER-COOLED NUCLEAR POWER PLANTS The Duquesne 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 REQUIREMENTS FOR PACKAGING,
- SHIPPING, RECEIVING,
- STORAGE, AND HANDLING OF ITEMS FOR WATER-COOLED NUCLEAR POWER PLANTS The Duquesne Light Company Operations Quality Assurance Program j
requirements follow the guidance of Regulatory Guide 1.38.
l Procedures and/or specifications were developed prior to, and implemented concurrent with the start of the operations phase.
REGULATORY GUIDE 1.39, MARCH 16, 1973:
HOUSEKEEPING REQUIREMENTS FOR WATER-COOLED NUCLEAR POWER PLANTS 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 REQUIRE RNTS 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 concurren~c with the start of the operations phase.
REGULATORY GUIDE 1.58, REVISION 1,
SEPTEMBER, 1980:
QUALIFICATION OF NUCLEAR POWER PLANT INSPECTION, EXAMINATION AND TESTING PERSONNEL Qualification of inspection, examination, a:id testing personnel at Beaver Valley Power Station (BVPS) follows the guidance of this regulatory guide with the following clarifications:
l ANSI N45.2.6, P_aracraph 2._E:
ANSI N45.2.6-1978 recommends that organizations identify any special physical characteristics needed in the performance of each
- activity, and that personnel requiring these characteristics have them verified by examination at intervals not to exceed one year.
At BVPS, examinations to verify personnel have the required physical characteristics will be scheduled on an annual basis with a
maximum allowable i
extension of 90 days.
1.3-49 1
ATTACHMENT 2 BVPS-1 UPDATED FSAR Reculatory Guide 1.58. Pa_raaraoh C.6:
j The initial qualifications of individuals to Levels I, II, or L
III will generally be to the education and experience recommendations of ANSI N45.2.6-1978.
However, in certain l
instances as determined by appropriate management, l
qualifications may alternatively be determined through test l
results and/or demonstration of capabilities.
Individual l
requalification will meet or exceed the recommendation of the standard.
l Paragraph 3.5.1 of ANSI N45.2.6 5978 lists recommended l
education and experience for qualification to Level I.
BVPS will also accept a
4-year college degree plus 1 month of l
related experience or equivalent inspection, examination, or testing activities.
REGULATORY GUIDE 1.64:
QUALITY ASSURANCE REQUIREMENTS FOR DESIGN OF NUCLEAR POWER PLANTS l
The Duquesne Light Company Operations Quality Assurance Program requirements follow the guidance of Regulatory Guide 1.64.
REGULATORY GUIDE 1.68, DRAFT 4, OCTOBER 2, 1973:
PRE-OPERATIONAL 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.
REGULATORY GUIDE 1.70.11:
INFORMATION FOR SAFETY ANALYSIS REPORTS QUALITY ASSURANCE SAFETY OPERATIONS PHASE The Duquesne Light Company Operations Quality Assurance Program requirements follow the guidance of Regulatory Guide 1.70.11.
REGULATORY GUIDE 1.88,
- OCTOBER, 1976:
COLLECTION, STORAGE, AND MAINTENANCE OF NUCLEAR POWER PLANT QUALITY ASSURANCE RECORDS The collection, storage and maintenance of quality assurance records at Beaver Valley Power Station will meet the intent of this regulatory guide with the following alternatives:
1.
The design and construction of quality assurance record storage facilities will follow the guidance of ANSI /ASME NQA-1-1983, Supplement 175-1, Section 4.4.
2.
When temporary stora e of records is required, the guidance of ASME NQA-1-1989, Supplement 17S-1, Section 4.4.3 will be followed.
1.3-50 l
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!s i
ATTACHMENT 3 BVPS-2 UFSAR
-TABLE 1.8-1-(Cont)
General membrane.. 1.5 S,
. Local membrane...the greater of 1.8S, or 1.5S,
Bending plus local membrane...the greater of 1.8S,or 1.5S,.
3.
The bellows assemblies were ' designed, fabricated, i
- tested, and installed to the following cricaria in lieu.
of the requirements of paragraphs C.2.a and b.
.The fuel.
transfer tube expansion bellows shall be in accordance With Code Case 1330-3 (special ruling) Special Equipment RequirementsSection III.
An N-2 form # ?. accordance with Code Case 1177 shall be furnished bj the bellows i
vendor.
A duplicate bellows shall be required for pressure and.. fatigue testing by the Contractor in accordance with ASME
- III, Winter 1974
- Addendum, paragraph NE-33 65. 2 (e) (2).
The 15-percent maximum i
convolution pitch in accordance with paragraph NE-3365.2(c) for unreinforced bellows.may be exceeded q
provided the bellows remain within the elastic range.
RG No. 1.58. Rev. 1 UFSAR Reference Sections 17.1, 17.2 OUALIFICATION OF NUCLEAR POWER-PLANT INSPECTION. EXAMINATION.
AND TESTING PERSONNEL (SEPTEMBER 1980) 1 Qualification of inspection, examination, and testing personnel at Beaver Valley Power Station (BVPS) follows the guidance of l
this regulatory guide with the following clarifications:
)
ANSI N45.2.6. Paraaraoh 2.5:
ANS1 N45.2.6-1978 recommends that organizations identify any special physical characteristics needed in the performance of each
- activity, and that personnel requiring these characteristics have them verified by examination at intervals not to exceed ono year.
At BVPS, examinations to verify personnel have the required physical characteristics will be scheduled on an annual basis with a
maximum
+
allowable extension of 90. days.
]
l Reaulatory Guide. 1.58 - Paracraoh C.6:
l The initial qualifications of individuals to Levels I, II, or III will generally be to the education and experience 4
recommendations of ANSI N45.2.6-1978.
However, in certain
' instances
_ as determined by appropriate management,
. qualifications-may alternatively be determined through test
-results and/or demonstration of capabilities.
Individual 1
requalification will meet or exceed the recommendation of
.the standard.
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ATTACHMENT 3 BVPS-2 UFSAR TABLE 1.8-1 (Cont)
Paragraph 3.5.1 of ANSI N45.2.6-1978 lists recommended education and experience for qualification to Level I.
BVPS l
will also accept a
4-year college degree plus 1 month of J
related experience or equivalent inspection, examination, or testing activities.
RG No. 1.59. Rev. 2 UFSAR Reference Section 2.4.2.2 DESIGN BASIS FLOODS FOR NUCLEAR POWER PLANTS (AUGUST 1977)
The determination of the design basis flood and the design of Beaver Valley Power Station - Unit 2 follow the guidance of this regulatory guide.
RG No. 1.60. Rev. 1 UFSAR Reference Section 3.7B.1.1 i
DESIGN
RESPONSE
SPECTRA FOR SEISMIC DESIGN OF NUCLEAR POWER PLANTS (DECEMBER 1973)
The design response spectra for the seismic design of Beaver Unit 2 meets the intent of Regulatory Valley Power Station Guide 1.60 with the following alternatives:
The horizontal design response spectra used for seismic analyses are shown on Figures 3.7B.1.1-1 and 3.7B.1.1-2.
The spectra shown for the safe shutdown earthquake (SSE) correspond to a
maximum ground acceleration of 0.125g and the spectra shown for the operating basis earthquake (OBE) correspond to a
maximum ground acceleration of 0.06g.
The vertical design response spectra are taken to be two-thirds of the horizontal design response spectra.
These response spectra are based upon the response spectra used for Beaver Valley Power Station - Unit 1 (Figures 2.5-1 and 2.5-2, BVPS-1 UFSAR, October 27, 1972 Docket 50-33A) and as revised in response to USAEC Regulatory Position 3 of May 25, 1973 (Question 3.15, BVPS-2 PSAR, Amendment 7, July 9, 1973).
32 of 80
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