ML20136F232
| ML20136F232 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/25/1984 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20136E513 | List: |
| References | |
| FOIA-84-663 NUDOCS 8410020702 | |
| Download: ML20136F232 (14) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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. Tcr Licensing 01v,.slon er Licensinc Office of fiuclear ^.esctor Re;u' ?.;icr.
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00 ket No. 50-424 and 50-425 l
MEMORANDUM FOR:
Thomas M. Novak, Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation FRCM:
J. Nelson Grace, Director Division of Quality Assurance, Safeguards, j
and Inspection Programs Office of Inspection and Enforcement
SUBJECT:
QA BRANCH INPUT FOR V0GTLE SER l
l Applicant:
Georgia Power Company (GPC)
Licensing Stage OL Responsible Branch LB #4 Project Manager:
M. Miller Review Status:
Complete (0penitemsnoted)
The QA Branch has completed its review of Chapter 17, " Quality Assurance," and the response to the 260 series of questions as presented through Amendment 9 of the Vogtle Electric Generating Station FSAR. The results of our review are described in the enclosed SER Chapter 17. Except as noted in Section 17.5 of f
the enclosure, we find the applicant's QA program description acceptable.
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Any questions concerning this review should be directed to Jack Spraul on X24530.
Original signed by j
1 Nelson Grace J. Nelson Grace, Director Division of Quality Assurance, Safeguards, and Inspection Programs Office of Inspection and Enforcement i -
Enclosure:
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6 QUALITY ASSURANCE
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V0GTLE SER l
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j 17.1 General '
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- 1 The description of the quality assurance (QA) program for the operations phase of the Vogtle Electric Generating Station is contained in Section 17.2 of the Final Safety Analysis Report (FSAR). Staff evaluation of this QA program through FSAR Amendment 9 is based on a review of this information and discussions with representatives of Georgia Power Company (GPC). NRC assessed GPC's QA program for the operations phase to determine if it complies with the requirements of 10 CFR Part 50, Appendix B, " Quality
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Assurance Criteria for Nuclear i aver Plants and Fuel Reprocessing Plants,"
the applicable QA related Regulatory Guides listed in Table 17.1, and the i-Standard Review Plan (SRP) Section 17.2, Rev. 2, " Quality Assurance
- .I During the Operations Ph&se."
a 17.2 Organization 1
The structure of the organization responsible for the operation of Vogtle and for the establishment and execution of the operations phase QA program is shown in Figure 17.1.
I The Executive Vice President-Power Supply is responsible for establishing 5
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the pclicies, goals, and objectives of the GPC QA program for Vogtle.
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He is the final management authority responsible for the development, implementation, changes to, and review of the operations QA program.
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!t The Senior Vice President-Nuclear Power and the Vice President and
- General Manager-Nuclear Operations are responsible to the Executive Vice i,
President-Power Supply for implementing the QA program for plant opera-
'1 tions at all nuclear power generating plants in the GPC system. The i
General Manager-Vogtle Nuclear Operations reports to the Vice President and General Manager-Nuclear Operations through -the Manager-Nuclear Operations.
i.4 The Manager-Nuclear Planning and Control reports to the Vice President
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and General Manager-Nuclear Operations. This position provides long r
range planning and scheduling of maintenance work to be performed at Vogtle and provides the corresponding long range manpower plan.
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The Manager-Nuclear Training reports'to the Vice President and General Manager-Nuclear Operations. This position provides training programs
-l to ensure compliance with regulations and standards and to ensure that nuclear operations personnel have the education, training, and skills to safely operate and maintain Vogtle.
f The Manager-Nuclear Engineering and Chief Nuclear Engineer is responsible d.c*.
to the Vice President and General Manager-Nuclear Operations for day-to-
" Q*
day monitoring of Vogtle activities includir.g interfacing in the areas of nuclear fuel management, procurement, and processing, i'
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\\. p' The General Manager-Vogtle Nuclear Operations is responsible to the Vice President and General Manager-Nuclear Operations for all activities at Vogtle, including implementation of the operational QA program requirements with the exception to controls that are assigned to the QA department. He is also responsible for the safe
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operation of Vogtle.
The plant staff (as described in SER Chapter 13) performs safety-related activities in accordance with written, approved procedures. QA require-ments are included in these procedures. The superintendents and supervisors in the Vogtle organization will be responsible for imple-menting the operational QA program for activities under their purview.
1 The Quality Control Supervisor, as a member of the plant staff, is i
responsible to t5.e General Manager-Vogtle Nuclear Operations for admini-stration and implementation of an effective quality control (QC)
-1 inspection program at Vogtle. QC specialists report to the Quality Control Supervisor. The QC organization is involved in day-to-day safety-related activities at Vogtle such as work planning meetings, plant review board meetings, and routine staff meetings.
The Vice President and Chief Engineer-Power Supply Engineering and a
Services is responsible for providing engineering and technical support d bn 3
SJ to the various power supply organizations. During Vogtle operation, he U
is responsible for the management of. design engineering support, the qualification of suppliers, and the review of procurement documents for quality requirements.
l The General Manager of Quality Assurance and Radiological Health and
. 'j Safety (GMQA), located at the general office, is responsible to the 2
Executive Vice President-Power Supply for assuring implementation of the operational QA program and for managing activities of. the GPC QA organization. He has a staff at the general office and a staff located at the Vogtle site to conduct QA activities. He keeps GPC management 1
informed on the effectiveness and implementation of the operational QA program.
The Vogtle QA Manager reports to the GMQA and is responsible for ensuring 3
that the operational QA program for Vogtle-is implemented by all parti-cipants. He assures that satisfactory QA programs are established and
. maintained by Vogtle plant management and that site activities conform i
to the QA programs and procedures.
He assures that satisfactory QA pro-i grams are established and maintained by contractors [such as Southern Company Services (SCS), Bechtel Power Corporation (BPC), and others] and i
suppliers of safety-related materials, equipment, and services. He maintains and controls the Vogtle QA Manual.
,.A SCS is the Vogtle architect / engineer during operation.
In addition,
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SCS provides QA support, including audits, supplier qualification and
-surveillances, and engineering procedure reviews. SCS also administers
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i the Vogtle contract for engineering services provided by BPC, Activities
'j within the SCS work scope are governed by SCS policy and procedures ai manuals ihich are reviewed and concurred with by the SCS QA organization.
The GPC GMQA performs or causes to be performed audits of these functions, i
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BPC is under contract to SCS to provide architect / engineering services.
y The work scope includes plant design, development of purchase recomenda-A tions for equipment and materials, administration of purchase orders p
resulting from SCS-developed purchase recomendations, and support of the i
SCS supplier surveillance functions by providing procurement surveillance 9
services for selected safety-related items. Activities within the BPC work
- j scope are governed by procedures manuals. The GPC GMQA performs or causes j
to be performed audits of these functions.
G1 el The GPC GMQA and the Vogtle QC Supervisor and their staffs have the 3
authority and organizational freedom to identify quality problems; initiate, recommend, or provide problem solutions through designated a
channels and verify implementation of satisfactory solutions; and to I
stop or control further processing, delivery, or installation of nonconforming material.
17.3 Quality Assurance Program a
o d
(F j The QA program for the operation of Vogtle describes the QA policies, fj t'
goals, objectives, and requirements to be implemented at the station in q
order to assure that safety-related activities are performed in a Mld controlled manner and documented to provide objective evidence of compli-ance with NRC regulations and guidance. The QA program is implemented by
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the QA Manual that includes the QA policies, procedures, and instructions.
9!
This document presents the detailed techniques and methods by which the requirements of Appendix B to 10 CFR Part 50 and the provisions of the s
NRC regulatory guidance shown in Table 17.1 are satisfied.
It is reviewed and concurred in by the Executive Vice President-Power Supply.
9 The QA program requires that QA documents encompass detailed controls for 4.
(1) translating codes, standards, and regulatory requirements into speci-4 fications, procedures, and instructions; (2) developing, reviewing, and approving procurement documents,-including changes; (3) prescribing all quality-affecting activities by documented instructions, procedures, or
...F drawings; (4) issuing and distributing approved documents; (5) purchasing items and services; (6) identifying materials, parts, and coniponents; 9
(7) performing special processes; (8) inspecting and/or testing material, i
equipment, processes, or services; (9) calibrating and maintaining measur-ing and test equipment; (10) handling, storing, and shipping items; (11) identifying the inspection, test, and operating status of items; j
(12} identifying and dispositioning nonconforming items; (13) correcting i
conditions adverse to quality; (14) preparing and maintaining QA records;
], g and (15) auditing activities that affect quality.
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s, The QA program requires the establishment and continuous implementation of the QA indoctrination, training, and retraining program to assure that persons involved in safety-related activities are knowledgeable in QA instructions and implementing procedures and demonstrate a high level of competence and skill in the performance of their quality-related activities.
Quality is verified through surveillance, inspection, testing, checking, and auditing of work activities using procedures, instructions, and/or checklists.
Inspections are performed by inspectors who have been qualified and certified in accordance with codes, standards, or company training programs.
4 The GMQA is responsible for the establishment and implementation of the j'
audit program. Audits are performed with written procedures or checklists by qualified personnel not having direct responsibility in the areas being 3
audited. The QA program establishes a comprehensive audit system to ensure that the QA program requirements and related supporting procedures are effective and properly implemented during operations. Audits include an objective evaluation of QA practices, procedures, and instructions; of work areas, activities, processes, and items; of the effectiveness of implementation of the QA program; and of conformance with policy directives.
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The QA program requires documentation of audit results and review by management having responsibility in the area audited to determine and j
take corrective action as required. Reaudits are performed to determine 1
that nonconformances are effectively corrected and that the corrective action precludes repetitive occurrences. Audit findings, wh1ch indicate quality trends and the effectiveness of the QA program, are reviewed by j
the GMQA and are reported to the Executive Vice President - Power Supply on a regular basis.
17.4 Conclusions j!
Based on the review and evaluation of the QA program descri t n cn d
t at:
I (1) The QA organization of GPC provides sufficient independence from cost j
q and schedule (when opposed to safety consideration &, authority to effectively carry out the operations QA program, and access to management at a level necessary to perform its QA functions.
(2) The QA program, including the list of safety-related structures, l
systems, and ccmponents to which it applies, describes requirements, procedures, and controls that, when properly implemented, comply
],4 with the requirements of Appendix B to 10 CFR Part 50 and with the e-4 t
acceptance criteria contained in SRP Section 17.2, Rev. 2.
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il Accordingly, the staff concludes, subject to resolution of the issues j,
identified in Section 17.5 below, that the applicant's description of
- j the QA picgram is in compliance with applicable NRC regulations and acceptable for the operations phase of the Vogtle Electric Generating
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li Plant.
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17.5 Outstanding QA Issues through FSAR Amendment 9 n.M y
1.
The response to NRC question 260.8 regarding comitments to h
Regulatory Guides concerning QA, provided in FSAR amendment 9, says: "See revised section 1.9."
The staff review of the revised 4
section 1.9 has resulted in the following outstanding issues.
2 W
A.
The first VEGP position regarding Regulatory Guide 1.33 states:
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" Conform for the QAP during design and construction. Refer to sections 13.4, 13.5, and 17.2."
addresses operations and is not generally applicable during i
design and construction. This position should be deleted or l
.j clarified.
B.
Clarification 5 (page 1.9-29) and exception 2 (page 1.9-32) to Regulatory Guide 1.33 both reference.. paragraph 3.4.2 of O.
ANSI 18.7. The clarification refers to the technical specifi-
- k. j cations and the exception refers to FSAR chapter 13.
In both G
cases GPC should identify anything in paragraph 3.4.2 that is not being comitted to.
ij C.
Clarification 16 (page 1.9-30) to Regulatory Guide 1.33 deletes
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words from the first sentence in the second paragraph of part 5.2.7 of ANSI 18.7. The clarification should not delete the j
words "which confonn to applicable codes, standards, specifi-cations, and criteria" which describe the written procedures.
D.
Clarification 24 (page 1.9-31) to Regulatory Guide 1.33 substitutes "an equivalent" for "the same" in paragraph t,
5.2.13.1 of ANSI 18.7.
GPC should identify who (i.e., by
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position title) determines equivalency.
E.
Clarification 24 (page 1.9-31) and exception 3 (page 1.9-33) to Regulatory Guide 1.33 are identical. They delete the guidance in paragraph 5.2.15 of ANSI 18.7 t' % view applicable procedures i
following an unusual incident udase it is an accident,
'i unexpected transient, signiff ch & ator error, or equipment
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malfunction which results it p re; t,1ble event. The clari-fication should be eliminateo and tne exception should be
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deleted or justified.
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n F.
Clarification 28 (page 1.9-32) to Regulatory Guide 1.33 refers q ' [O. j to clarification 18 (page 1.9-31). The reference should be l
7 to clarification 19. Also, GPC should identify anything in j
part 5.2.19(3) of ANSI 18.7 that is not being committed to.
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Clarification 2 (page 1.9 37) to Regulatory Guide 1.38 stat S
that " equipment used to measure secondary conditions, such as warehouse temperature, (warehouse?) humidity, etc., will I
... not be maintained under the calibration and control program." GPC should' justify this position.
l H.
Clarification 4 (bottom of page 1.9-37) to Regulatory Guide 1.38 0
refers to "the clarifications of Paragraph 3.2.1, D and E above..." This reference should be deleted or clarified since j
there appears to be no clarification of paragraph 3.2.1, D or E.
dM I.
Clarification 6 (page 1.9-38) to Regulatory Guide 1.38 refers q
to " Regulatory Guide 1.37 (section 1.9) for the VEGP position-
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"regarding nonhalogenated materials in contact with austenitic
,I stainless steel." This reference should be clarified or deleted as GPC's position ~on Regulatory Guide 1.37 does not appear to address this subject.
't J.
Clarification 11 (page 1.9-38) to Regulatory Guide 1.38 does not allow storage of hazardous material in close proximity to
" installed systems required for safe shutdcwn"rather than in close proximity to "important nuclear plant areas." This appears to be a departure from of ANSI N45.2.2 which should be
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clarified, deleted, or justified.
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Clarification 13 (page 1.9-39) to Regulatory Guide.l.38 addresses rotating equipment. GPC should identify what is q
being clarified.
L.
Clarification 14 (page 1.9-39) to Regulatory Guide 1.38 indicates that dynamic load tests for rerating hoisting equipment will use the lift weight rather than 110Y. of the lift weight as stated in ANSI N45.2.2. This should be deleted or justified.
g M.
Exception 1(page1.9-40boRegulatoryGuide1.38 states l
that VEGP "may choos~e to protect weld-end preparation stored."
Item 7 of part 1.2.1 of ANSI M45.2.2 states that " weld end preparations all be protected <...." This exception should be deleted o justified.
N.
The VEGP position (page 1.9-40) regarding Regulatory Guide 1.39 indicates that burning and cutting pennits_ are substituted for fire watches. This appears to be a departure from subdivision
'3.2.3 of ANSI N45.2.3. Regulatory Position 2 of Regulatory Guide 1.39 states that subdivision 3.2.3 of ANSI N45.2.3 is not included as part of the Regulatory Guide 1.39, therefore this position
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should be deleted or justified. The second part of this position l
x states, " Refer to chapter 17 for further discussion," and this (t
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statement should be deleted or made more specific such that its i :
acceptability can be ascertained.
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Clarification 1 (page 1.9-51) of Regulatory Guide 1.58 refers
. to "other FSAR requirements". This reference should be deleted h
or made more specific such that its acceptability can be ascertained.
1 P.
Clarification 3 (page 1.9-51) of Regulatory Guide 1.58 exempts I
I inspection, examination, and testing personnel (except NDE personnel) from the 3-level classification portion of ANSI M45.2.6 with no justification or alternative. GPC should provide one or the other or delete the clarification.
Q.
-Clarification 4 (page 1.9-51) of Regulatory Guide 1.58 addresses qualification of inspectors. GPC should comit to verify that the training and experience of inspection,
.i examination, and testing personnel will assure their ability to perform the assigned work.
R.
The VEGP position (page 1.9-57) on Regulatory Guide 1.64 states that the " operations QAP conforms with the intent" of the guide. The words "the intent" should be deleted or clarified, f
S.
The VEGP position (page 1.9-71 and 1.9-74) on Regulatory i
j Guides 1.88 and 1.94, respectively, should be clarified to show GPC's comitment to comply with the guides during the operations phase. The comitments are not clear as provided.
I T.
Clarification 3 (page 1.9-92) of Regulatory Guide 1.123 refers to "an equivalent level" of review and approval of changes to procurement documents. GPC should clarif level" means and who (by position title) y what " equivalent determines equivalency.
U.
Clarification 7 (page 1.9-92) of Regulatory Guide 1.123 states that GPC wishes to replace paragraph 4.2(a), (b), and (c) of i
ANSI M45.2.13 with the paragraphs shown on pages 1.9-92,
[-
1.9-93, and 1.9-94.
GPC should identify anything in paragraph j
4.2 of the standard that is not being comitted to. Replacement
~j paragraph b(5) (page 1.9-93) states: "Aninspection(ofoff-the-shelf items) shall be performed to assure that the correct 1
item was received and no damage exists." We note that a typical
" identity and damage" inspection may be inadequate to assure that an off-the-shelf item will perform its required safety
~ function. This paragraph needs expansion to describe how GPC assures that off-the-shelf items will perform satisfactorily.
V.
Clarficiation 8 (page 1.9-94) of Regulatory Guide 1.123 is unclear because of the last word, " intent". This word should be deleted or explained.
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Clarification 9 (page 1.9-94) of Regulatory Guide 1.123 describes an exception to paragraph 5.3 of ANSI N45.2.13 regarding h
preaward evaluations. GPC should describe controls which
,F prevent the exception from becoming the rule.
X.
Clarification 10 (page 1.9-94) of Regulatory Guide 1.123 gives alternative methods to the requirements of paragraph 6.1 of ANSI N45.2.13 for monitoring and evaluating supplier performance (7.1 in the clarification should be 6.1). The alternatives do
-2 not appear to cover the areas of change control and the establish-ment of an exchange method of document information between supplier and purchaser. These apparent omissions should be justified or eliminated.
Y.
Clarification 16 (page 1.9-95) of Regulatory Guide 1.123 adds limitations to paragraph 8.2 of ANSI N45.2.13. The limi'tation
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concerning supplier submittal of noncoformance information only 1
if the end use is affected presumes the supplier has knowledge of end use information which he may not have. The definitions at the bottom of page 1.9-96 require inspection and/or test regarding end use, but it is not clear that the supplier will have the required information. GPC should clarify how it assures gg the supplier has such infonnation.
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Clarification 17 (page 1.9-96) of Regulatory Guide 1.123 is not clear when it comits conformance to paragraph 10.2 of ANSI N45.2.13 "to the extent that the certificate of compliance is traceable to the purchase order." Paragraph 10.2 addresses certificates of conformance which are not addressed elsewhere in the standard, and the second sentence 'in the clarification is also not clear. GPC should explain the clarification.
AA. The VEGP position relative to Regulatory Guide 1.144 (page 1.9-110) indicates conformance to draft 11, revision 0, of 1
ANSI N45.2.9-1973. This conflicts with the comitment to revision 2 of Regulatory Guide 1.88 (page 1.9-71) as noted in I.
item S above. The VEGP position should show a commitment to j
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BB. The table below shows where GPC has committed in FSAR section 1.9 to do something else rather than follow the specific NRC guidance / ANSI standard. In each case GPC should identify.
anything in the specific NRC guidance / ANSI standard not being s
comitted to that is not included in the commitment to something else.
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' Reg Guide /
FSAR No comitment to Comitment ANSI Std.
pg/ item paragraph no.
instead to I
(1) 1.30/N45.2.4 1.9-26/1 2.2 Appropriate FSAR section (2) 1.33/N18.7 1.9-29/6 4.1 Technical Specifications (3) 1.33/N18/7 1.9-29/7 4.3.1 Technical Specifications (4) 1.33/N18.7 1.9-29/8 4.3.4 Technical Specifications (5) 1.33/N18.7 1.9-29/9 4.4 Technical Specifications (6) 1.33/N18.7 1.9-29/10 4.5 Technical Specifications, FSAR Section 17.2 and Reg Guide 1.144 (7) 1.33/N18.7 1.9-29/,12 5.2.2 Technical Specifications (8) 1.33/N18.7 1.9-29/13 5.2.6 FSAR Section 17.2 (9) 1.33/N18/7 1.9-31/19 5.2.8 Technical Specifications 7
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(10) 1.33/N18.7 1.9-32/27 5.2.18 FSAR Section 17.2 and V
Reg Guides 1.37, 1.39, and 1.54 (11)1.33/N18.7 1.9-32/29 5.2.19.1 FSAR Sections 17.2 and 14.2 and Reg Guides 1.30, 1.58, 1.94 and 1.116 i>
(12) 1.33/N18.7 1.9-32/30 5.38 Technical Specifications j
(13) 1.33/N18.7 1.9-32/32 5.2.10 FSAR Section 17.2 e
(14) 1.37/N45.2.1 1.9-35/1 2.5 FSAR Section 17.2 (15) 1.37/N45.2.1 1.9-35/3 9
Reg Guide 1.88 (16) 1.38/N45.2.2 1.9-37/1 2.3 FSAR Section 17.2 (17)1.116/N45.2.8 1.9-86/1 4.4 FSAR Section 17.2 (18) 1.123/N45.2.13 1.9-92/6 3.4 FSAR Section 17.2 (19)1.123/N45.2.13 1.9-95/12 6.4 The Operations QAP
],
(20) 1.123/N45.2.13 1.9-95/13 7.4 FSAR Section 17.2
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FSAR No commitment to Comitment ANSI Std.
pg/ item paragraph no.
instead to
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(21) 1.123/N45.2.13 1.9-95/14 7.5 Reg Guide 1.58
('22) 1.123/N45.2.13 1.9-96/18 12 Reg Guide 1.144 3
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2.
The response to NRC questions 260.61 and 260.62 regarding the items controlled by the GPC QA program was provided in FSAR Amendments 8 and 9 respectively. The staff review of the response has resulted in the following items which require a commitment from GPC that the pertinent j
provisions of its operational QA program will be applied during the l:
operations phase, tJ A.
Site drainage system alterations (Item 260.61.A.3) t B.
Accident related meteorological data collection equipment (Item 260.61.A.7)
C.
Radiation protection systems (Item 260.61.A.8)
D.
Instrumentation to satisfy the requirement of part III.D.3.3 of NUREG-0737 (Item 260.61.C.18)
U E.
Containment building polar bridge crane components that perform a safety function (Item 260.62.A.6) i F.
Reactor coolant pump seals (Item 260.62.A.8)
~
G.
Shell side of letdown heat exchanger of the CVCS (Item 260.62.B.1)
H.
Shell side of excess letdown heat exchanger of the CVCS (Item 260.62.B.2)
I.
Shell side of seal water heat exchanger of the CVCS (Item 260.62.B.3) a J.
Auxiliary component cooling water surge tank (Item 260.62.B.4) j K.
Auxiliary component cooling water pumps (Item 260.62.B.5)
L.
Refueling machine (Item 260.62.8.6)
M.
Fuel transfer system (Item 260.62.B7) h.
Distribution panels of the 120-Vac power system-Class 1E (Added -
after-transmittai of-260d2 this-item-harnot-been-addresse&-
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Table 17.1 Regulatory Guides Applicable to QA Program 1.
Regulatory Guide 1.8, Rev.1-R, " Personnel Selection and Training" (5/77).
2.
Regulatory Guide 1.26. Rev. 3. " Quality Group Classifications and stan-dards for Water, Steam, and Radioactive-Waste-Containing Cosponents of Nuclear Power Plants" (2/76).
~
3.
Regulatory Guide 1.29. Rev. 3. *$eismic Design Classification" (9/78).
4 Regulatory Guide 1.30,l* Quality Assurance Requirements for the Installa-4]
tion, inspection, and Testing of Instrumentation and Electrical Equipment" 4
(8/72).
Regulatory) Guide 1.33, Rev. 2. " Quality Assurance Program Requirenents 5.
(Operation " (2/78).
6.
- Quality Assurance Requirerents for cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants" (3/73).
7.
Regulatory Guide 1.38. Rev. 2. " Quality Assurance Requirements for Pack-aging Shipping, Recetvin, Storage, and Handling of Itecs for Water-Cooled huc ear Power Plants" (5/ 7) 8.
Regulatory Guide 1.39. Rev. 2. "Heusekeeping Requirements for Water-Cooled l
Nuclear Power Plants" (g/77).
9.
Regulatory Guide
. Rev.1. " Qualification of Nuclear Power Plant Inspection Examination, and Testing Personnel * (9/80).
10.
Regulatory Guide 1.64. Rev. 2. "Qualit Design of Nuclear Power Plants" (6/76)y Assurance Requirements for the
- 11. Regulatory Guide 1.74, " Quality Assurance Terms and Definitions" (2/74).
- 12. Regulatory Guide 1.88 Rev. 2. " Collection, Storage, and Maintenance of t
Nuclear Power Plant Quality Assurance Recorcs" (10/76).
- 13. Regulatory Guide 1.94, Rev.1. " Quality Assurance Requirements for Instal-lation, Inspection, and Testing of Structural Concrete and :;trvetural Steel During the Construction Phase of Nuclear Power Plants" (4/76).
14 Regulatory Guide 1.116. Rev. 0-R, " Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems" (6/76).
f*
- 15. Regulatory Guide 1.123. Rev.-1, " Quality Assurance Requirements for Control of Procurement of items and Services for Nuclear Power Plants" (7/77).
.16.
Regulatory Guide 1.144. Rev.1 " Auditing of Quality Assurance Programs for Nuclear Power Plants" (9/80) 17 Regulatory Guide 1.146, " Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants" (8/80).
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