ML20067A647
| ML20067A647 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/08/1984 |
| From: | Greher E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Miller W NRC OFFICE OF ADMINISTRATION (ADM) |
| Shared Package | |
| ML082420195 | List:
|
| References | |
| FOIA-90-162 NUDOCS 9102070343 | |
| Download: ML20067A647 (83) | |
Text
..
g UNITED STATES
~['
NUCLEAR REGULATORY COMMISSION 5
WASHING TON, D. C. 20$55 t\\
SfR/RV HEMORANDUM FOR:
William Miller, Chief c g@ / g,W.
Licensee Fee Management Branch Office of Administration y) f 3 _
g-FROM:
Elliott A. Greher, Program Analyst g rv, 3 ',
Program Support and Analysis Staff Office of Inspection and Enforcement L/4
SUBJECT:
REQUESTED LICENSE FEE INFORMATION We have reviewed available records on IE staff effort -- staff or IE consultants assigned to IE headquarters or to the-Technical Training Center -- devoted to license fee-billable efforts for the reactor license Vo(me-1 docket number so - w/
during the period =
6 / > s/ 7 v to c/n/t v r
(
)
There is no record of IE staf f effort.
(X)
There is IE staff effort and it is all devoted to IE functions.
A total of d / 6. 0 - hours of effort is recorded.
See enclosed computer run for the details,
(
)
There is IE staff effort and it is all devoted _to regional functions.
The appropriate computer run has been mailed to region-1
(
-)
There is IE staff effort'and it is devoted in part to IE functions.
A total ~of hours of effort is recorded.
See enclosed computer run for details. There is-also IE staff effort devoted to regional functions. The appropriate computer run has-been mailed to region
( K)
We are still searching available contractor. cost records-and expect to )rovide that information to you -and to the regions, as appropriate wit 11n three weeks.
(
)
There is no record of IE computer costs.
(
)'
There are IE contractor costs.
See enclosed information.
A.-
) iott A.
reher, Program Analyst Program Support and Analysis Staff Office of Inspection-and Enforcement
Enclosures:
PQ
[ gyp 900921 As stated WILLIAN90-162 PDR 1
cc w/o enclosures:
J. L. Blaha, IE A. J. Burda IE M h mi,/PJr
i 07/31/84 MPS. DATA FOR V0GTLE 1 (50/424)
PAGE JUN 28, 1974 TO JUNE 23, 1984 WK ORG SOC-SEC
'ACT REG NON-REG TOTALHRS ENDING CODE NO CODE HRS HRS 010784 I112 LRA 4.0
.0 4.0
+
t WZ-END TOTAL 610784 1112 LRA 4.0
.0 4.0 021184 I112' LRA 1.0
.0
- 1. 0 i l
WZ-END TOTAL 021184 I112 LRA 1.0
.0 1.0 032484 I261 LRA 14.0.
4.0 18.0 r
-4K-END TOTAL 032484 I241 LRA 14.0 4.0 18.0 040784 1112-LRA 12.0
.0 12.0 I WK-END TOTAL 040784 1112 LRA 12.0
.0 12.0 040784 1113 LRA 21.0 17.0 38.0
.WK-END TOTAL 040784 I113 LRA 21.0 17.0 38.0 f
-040784 I241 LRA 8.0 4.0 12.0 TOTAL 040784 1241 LRA' 8.0 4.0 12.0 I
f W%-END 5
i 041484 I112 LRA 9.0
.0 9.0 j'
i WK-END
' TOTAL 041484 I112 LRA 9.0
.0 9.0-
[
l 041484 Itt3 LRA
.0
-10.0 10.0.
i' WK-EhO TOTAL 041484 I113 LRA
.0 10.0 10.0 l
f I
041484 I241 LRA 25.0 3.0 28.0
~
'WK-END
- TOTAL 041484 1241 LRA 25.0 3.0 28.0 7
042184 1241 LRA 6.0 2.0 8.0 6.0 2.0
-8.0 WK-END TOTAL 042184 1241 LRA 042884 1112 LRA 1.0
.0 1.0 i """
LRA 1.0
.0 1.0 i
WK-END TOTAL 042884 1112 i
042884 1241 LRA 2.0
.0 2.0 WK-END TOTAL C42884 1241 LRA 2.0
.0 2.0
.I l
I C 4
j k.
i) l-
.l
07/31/84 MPS DATA FOR V0GTLE 1 (50/424)
PAGE JUN 28, 1976 TO JUNE 23, 1984 WK ORG SOC-SEC ACT REG NO REG TOTALHRS ENDING CODE NO CODE HRS HRS 050584 1112 LRA 3.0
.0 3.0 W%-END TOTAL 050584 1112 LRA 3.0
.0 3.0 051984 I241 LRA 8.0 2.0 10.0 W%-END TOTAL 051984 I241 LRA 8.0 2.0 10.0 060284 1112 LRA 9.0
.0 9.0
.WK-END TOTAL 060284 1112 LRA 9.0
.0 9.0 061684 1111 LRA 9.0 1.0 10.0 WK-END TO TAL 061684 1111 LRA 9.0 1.0 10.0 071633 It13 LRA 2.0
.0 2.0 WK-END TOTAL 071683 1113 LRA 2.0
.0 2.0 C81383 1113 LRA 2.0
.0 2.0 WK-END TOTAL 081383 Itt3 LRA 2.0
.0 2.0
~
100183 I113 LRA 1.0
.0 1.0 WC-END TOTAL 100183 I113 LRA 1.0
.0 1.0 100883 1241 LRA 12.0
.0 12.0 i
12.0
.0 12.0 J%-END TOTAL 100883 1241 LRA 24.0
.0 24.0 101583 I241 LRA 3.0
.0 3.0 3.0
.0 3.0 5
WK-END TOTAL 101583 I241 LRA 6.0
.0 6.0 111283 1113 LRA 5.0
.0 5.0
~~WK-END TOTAL 111283 1113 LRA 5.0
.0 5.0
. 111983 1113 LRA 26.0
.0 26.0 WK-END TOTAL 111983 Itt3 LRA 26.0
.0 26.0 7
~
07/31/84 MPS DATA FOR V0GTLE 9 (50/424)
PAGE JUN 28, 1976 TO JUNE 23, 1984 4
_=______
ENDING CODE H0 CODE HRS HRS 112683 1113 LRA 2.0
.0 2.0 Wl-END TOTAL 112683 I113 LRA 2.0
.0 2.0 121083 1111 LRA 3.0 8.0 11.0 WK-END TOTAL 121083 1111 r LRA 3.0 8.0 11.0 121783 1111 i LRA 3.0 8.0 16.0 WK-END TOTAL 121783 1111 LRA 3.0 8.0 16.0 121783 1113 LRA 5.0
.0 5.0 WK-END TOTAL 121783 I113 LRA 5.0
.0 5.0 "bgp I
i l
l l
l l
l l
l i
u 1
07/31/84 MPS DATA FOR V0GTLE 1 (50/424)
PAGE.
~JUN 286 1974 TO JUNE 23, 1994 WK ORG.
SOC-SEC-ACT.
REG.
HON-REG
-TbT LHRS ENDING CODE NO CODE HRS HRS'
.. BRAND ~-TOTAL.
216.0 59.0 275.0 I.
4 1
)
i 4
4
?
.f L-l W S rpfle ^ @jl '
L
~
~-
L S 2. - _.
E ? u m a cr S$--
h emp i
e
+
L 10/19/84 c
i Region 11-Jimt For the Region 11 cases listed below all professional hours shown.as.QAT or 3BH j
should be' excluded from the OL reviewicomputation becense - Chapter-.17.
1..
of the SER refers to the licensee's-topical report.
I'mgetting'copiesofthh Chapter 17 pages from the updated FSAR retained by the Records:Section.
(Docket Files) and will:let you-see them when they arriver
.q 1
1.
TVA Bellefonte 1 & 2 - Topical Report; Number-TVA-TR-75 - Watts Bar 1 & 2 - Topical Report Number-TVA,TR-75?l-2.
Duke Power - Catawba 1 & 2 '. Topical Rhpert Number-OllKE-1 3.
Mississippi Power -- Grand Gulf 1- & 2 - Topical Report Number-MPL-TOP-1
- f I don't find that there are topicals for QA on Harris 1 &.'2 or
- Vogtle-IL& 2 g
'but I am getting Chapter 17 pages to see~what the:FSAR says.
Florida Power 1&-
Light and VEPCO.also have topical' reports,'but they de.netJhaie:eni-OL appli-cations under review 'hus these two are'not at. issue..-1-plan to look~at jhe t
revisions / amendments.to the topical reports for which feet have.been collected and will-determine'iflthe feesLassessed cover the latestfamendments' filed or.
approved
.i b
Reba-I' 5
O
,.:_.+ --.
, :. L..
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[ jc,b VEGP-FSAR-17 g u fS4A 17.2 OPERATIONS QUALITY ASSURANCE PROGRAM S 2p"gt,j,Er A Georgia Power Company (GPC) has a total quality program-to /
4[ / A establish and maintain standards of quality covering the
- ..)
engineering, design, procurement, manufacturing, construction, jcA /~
andmodificationsof-@,,fg testing, maintenance, repair, refueling, applicable structures, components, and systems for VEGP, As
/
the licensee, GPC assumes full responsibility for the quality & }'
program and will take appropriate action to guarantee that VEGP is designed, constructed, and operated with sound engineering
~)
principles and safe operating practices.
The responsibility for establishing the program policies, rdd goals, and objectives, as summarized below, is. vested in the CPC executive vice president-power supply.
7 yL A.
All participants in the quality assurance program, including suppliers and contractors, shall meet Mg-appropriate sections-of 10 CFR 50, Appendix B M
- criteria,
~
,J,'
B.
The program described herein shall be documented by written procedures or instructions.
C.
The quality assurance program shall provide control over activities affecting the quality of structures, systems, and components consistent with their importance to safety.
D.
Activities affecting quality shall be accomplished under controlled conditions which include the use of appropriate equipment, suitable environmental conditions, and assurance that prerequisites for the given activity'have been satisfied.
E.
The quality program shall take'into account the need for special controls, processes, test equipment, g,
tools, and skills to attain the required quality.
F.
. Verification of conformance to established requirements shall be accomplished by individuals or groups who do not have direct responsibil-ity for performingtheworkbeingvgrifie
,*)
The quality program shall devidt for indoctrination G.
and' training of personnel
'forgng$ctivities affecting quality, as nece ry fip ergure that suitable proficiency is ac vecNand,1Ipaintained.
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i 17.2.1-1
1 VEGP-FSAR-17
- \\
H.-
Management shall regularly review the, status,-
adequacy, and implementation of the quality-program through the quality assurance auditing process.
.c This section describes the operations' quality assurance program V*
(OQAP) for VEGP.
It defines responsibility and authority and prescribes measures for the control and accomplishments of activities affecting the quality of safety. structures, systems, and components of VEOP.
The OQAP requirements herein are implemented in-approved procedures, which provide requiremants for the performance of' safety-related activities.- The OQAP is P-implemented by GPC and executed by various responsible parties-to ensure the plant's safe and reliable' operation and to satisfy the quality assurance requirements of Appendix B of 10 CFR 50, as delineated in Regulatory Guide 1.33, Revision 2, Quality Assurance Program Requirements (Operation).
American National Standards Institute N18.7-1976,; Administrative a
Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants, was used for guidance in developing the OQAP.
The organizational structure of GPC is described in section 13.1.
The following' subsection amplifies upon section 13.1 with regard to' establishment and execution of the OQAP.
17.2.1 ORGANIZATION The principal elements-. implementing the OQAP -are as follows:
o Corporate organization, e
^4uclear operations.
Plant staff.
8 o
Engineering and construction services, e
Vogtle Project organization, k
Quality assurance department.
e Figure 17,2.1-1 shows the relationship of the above elements involved in the OQAP.bg
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17.2.1.1 Corpora 51on" organization EA The executive vice president-power supply is the-final management; authority (disponsible forithe development, p
implementation, chang s,to,'and review of the OQAP.
These Rb I
17.2.1-2 Amend. 8 7/84
.q}
VEGP-FSAR-17 i
responsibilities are accomplished through the organization shown in figure 17.2.1-1 and are discussed in the following paragraphs, g.a-)
GPC's executive vice president-power supply regularly assesses the scope, adequacy, and compliance of the OQAP to 10 CFR 50,'
Appendix B, through frequent meetings with the general manager-quality assurance and radiological health and safety (GMQA), review of safety review board activities, and assessment j
of quality assurance audits.
i An annual assessment of the effectiveness of the OQAP is performed by the general manager-quality assurance, and results are reported to the executive vice president-power supply.
17.2.1.1.1 Safety Review Board The safety review board shal'1 be appointed by the executive vice president-power supply for the purpose of advising him in matters related to nuclear power plant safety.
Board members shall have competence in various fields of engineering technology and be familiar with nuclear safety, environmental, 3
)
and regulatory requirements.
The safety review board has access to the advice and services of technical specialists within GPC 8
and outside expertise as necessary.
Board member responsibilities and authorities are described in the plant Technical Specifications.
17.2.1.1.2 Nuclear Operations The senior vice president-nuclear power and the vice president and general manager-nuclear operations are responsible to the executive vice president-power supply for the implementation of the quality assurance program for plant g..
operations at all nuclear power generating plants in the GPC v.g.
system.
The general manager-Vogtle nuclear operations reports to the vice president and general manager-nuclear operations i
through the manager-nuclear operations,.
The manager-nuclear operations assumes the responsibilities of vice president and general manager-nuclear operations in his absence.
- N Q:)
The manager-nuclear planning and control reports to the vice president and general manager-nuclear _ operations.
Some of the responsibilities of this position are to provide long range planning and scheduling of maintenance work to be performed at GPC nyclear plants and to provide the long range manpower plan for GPC nuclear plants.
ra,)
17.2.1-3 Amend. 8 7/84 1
\\
1 VEGP-FSAR-17 The manager-nuclear training reports to the vice president and general manager-nuclear operations.
A few of the responsibilities of this position are to provide the GPC nuclear plants with training programs to ensure compliance with Nuclear Regulatory Commission (NRC) regulations and Institute of Nuclear Power Operations standards and to ensure that nuclear 8
operations personnel have the education, training, and skills to safely and efficiently operate. and maintain the plants.
The manager-nuclear engine,ering and chief nuclear engineer is responsible to the vice president and general manager-nuclear operations for day-to-day monitoring of plant activities, special projects as required, licensing support, and interfacing with appropriate companies and organizations in the areas of nuclear fuel management, procurement, and reprocessing.
17.2.1.2 Plant Organization The plant staff (as described in chapter 13) will perform safety-related activities in accordance with written, approved p rocedu re s.
Quality assurance requirements will be included in detailed plant procedures.
The superintendents and supervisors in the VEGP organization will be responsible for implementation of the OQAP for activities under their purview.
The general manager-Vogtle nuclear operations will regularly assess the workload of all departments involved in the OQAP to ensure that a sufficient number of personnel are available,for complete and efficient implementation, 17.2.1.2.1 General Mahager-Vogtle Nuclear Operations and Assistant Plant Manager (s)
The general manager-Vogtle nuclear operations is responsible to the vice president and general manager-nuclear operations for 8
all activities at the VEGP, including implementation of the OQAP requirements with the exception to-controls that are assigned to N
the quality assurance department.
The general manager-Vogtle nuclear operations is also responsible for the safe, reliable, and efficient, operation of VEGP.
17.2.1.2.2 Quality Control Supervisor The quality control supervisor is responsible to the general manager-Vogtle nuclear operations for administration and implementation of an effective quality control inspection program at VEGP.
Quality control specialists report to the quality control supervisor.
The quality control supervisor, or his representative, is involved in day-to-day safety-related 17.2.1-4 Amend. 8 7/84
')
VEGP-FSAR-17 activities.
Tnese activities include work planning meetings, plant review board meetings, and routine staff meetings.
8 Quelity control personnel have procedural authority to stop work 3) and to control further processing, use, or installation of nonconforming items.
17.2.1.2.3 Superintendent of Maintenance
)
The superintendent of maintenance is responsible for effective implementation of the OQAP of applicable mechanical, electrical, and instrument and controls maintenance of plant equipment, systems, or structures.
17.2.1.2.4 Superintendent of Operations The superintendent of operations has the responsibility to ensure that the plant is operated in accordance with approved procedures and license requirements.
17.2.1.2.5 Superintendent of Plant Engineering Services s
The superintendent of plant engineering services is responsible for providing engineering-related technical services in support of VEGP operations.
He shall assist, as required, in the procurement of equipment, materials, and services and shall coordinate review, approval, and closecut of design changes.
17.2,1,2.6 Superintendent of Administration The superintendent of administration has the responsibility of maintaining the plant documentation files, procedure and change logs, and distribution control for plant-originated procedures,
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plant review board minutes, and correspondence.
.:p 17.2.1,2.7 Materials Supervisor The materials supervisor is responsible for material and
, +
'.)1 equipment control and material requisitioning to maintain plant etock levels.
He is also responsible for receiving, handling, and storing materials.
17.2.1.2. 8 Superintendent of haclear Training
,l,)
The superintendent of nuclear training is responsible for the development and implementation of training programs for the 17.2.1-5 Amend. 8 7/84
H VEGP-FSAR-17 6
- 0 plant staff.
He ensures that-the VEGP_ training programs are adequate to provide qualified personnel.
R 9
17.2.1.2.9 Superintendent ' of Regulatory Compliance T
The superintencent of regulatory compliance will advise. plant management on matters concerning compliance with requirements-of operating license, Technical Specifications, approved plant procedures, Security Plan, Emergency Plan, OQAP, and applicable:
f federal, state, and local regulations.
9 17.2.1.2.10 Superintendent of Health Physics and Chemistry B
The superintendent of health physics'andLchemistry is responsible for the health physics and-chemistry program.
He is also responsible for the as-low-as-reasonably-achievable program at VEGP.
I 17.2.1.2.11 Plant Review Board The plant review board shall be comprised of responsible, plant department personnel and shall advise.the plant madager on matters pertaining to safety-related activities.
17.2.1.3 Quality Assurance Department The quality assurance department,-under the direction of the GMQA, verifies implementation of the OQAP.
The qualifications for the GPC quality assurance department L
personnel meet the requirements of Regulatory Guide 1.146, Qualification of Quality Assurance Program Audit-Personnel'for Nuclear Power Plants, as_ described in section 1.9.
The minimum qualifications for the GMQA and the.VEGP quality.
assurance. manager are that they' hold an engineering;orf equivalent degree-and have-a minimum ofLS years experience in the areas of engineering, field construction,'or plant operation.
Two of'these 5 years'must be.in the field of quality assuranco, _ o f, which at least 6 months.must be in.the. field _of
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nuclear quality assurance experience.
The size of the quality assurance _ organization is based on E
meeting the commitment-for audit coverage required by the Technical Specifications and on experience gained at Hatch Nuclear Plant.
The approximate size of the site quality
['
assurance organization is 10 technical people =for Unit 1:
17.2.1-6 Amend. 8 7/84
,,w<
[)
VEGP-FSAR-17 lg operation and will increase to approximately 15 when Unit 2 becomes operational.
.s
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The corporate quality assurance engineering / support groups i
provide technical and administrative support to the quality assurance department in the performance of its assigned responsibilities, imi 17.2.1.3.1 General Manager of-Quality Assurance and Radiological Health and Safety The GMQA, located at the general office, is responsible to the executive vice president-power supply for assuring implementation of the OQAP and for managing activities of the GPC quality assurance organization.
The GMQA can effectively 3
assure conformance to the quality assurance requirements and is l8 free from undue influence and from responsibility for cost and schedules.
The GMQA has a staff at the general office and a staff located at the site to conduct quality assurance activities.
The GMQA has been given authority by the executive vice president-power' supply to stop, in a timely manner, work on the VEGP site which is not being performed in accordance with
. -)
the provisions of the OQAP.
The GMQA keeps management informed on the effectiveness and implementation of the OQAP through distribution of audit reports and other documents.
Specific duties and responsibilities of the'GMQA are as follows:
A.
Manages the GPC quality assurance department.
B.
Develops.the quality assurance portions of OQAP to conform to approved policies.
C.
Approves the GPC VEGP Quality Assurance Manual and changes thereto.
D.
Maintains close liaison with the general manager-nuclear operations to ensure that program policies and procedures are being implemented and enforced.
8 cf y E.
Keeps the executive vice president-power supply
".')
informed orally on routine matters, but reports significant items immediately, both orally and in writing.
In addition, major audit reports, including summaries of audits by maj or contractors, are forwarded to the executive vice president.
'"[h F.
Informs management of quality assurance activities through distribution of audit reports and other correspondence.
17.2.1-7 Amend. 8 7/84
VEGP-PSAR-17 17.2.1.3.2 VEOP Quality Assurance Manager The VEGP quality assurance manager i that the approved quality assuranc s responsible for ensuring all participants.
The VEGP quality assurance managee programs are im assigned by the GMQA.
written stop-work authority.
The VEGP quality assurance manager h r is nonconforming materials, control of further processing, This authority provides for the as delivery, installation of installatienor reactor system when such further proor operation of a nu 8
safety or may, lead to the deterioratior operation may jeopardize plant cessing, delivery, em system.
This authority is defined in the VEGPon of a nuclear safety sonnel 7
Manual.
Quality Assurance Duties and responsibilities of the VE manager include but are not limited to thGP quality assurance e following:
A.
Mana'ges the VEGP quality assurance b.
organization, Assures that satisfactory quality as are established, maintained, surance programs between the'GMQA and plant managemand properly coordinated ent.
C.
Reviews and concurs with quality Company Services (SCS), contractors (Bechtel Power Corpo Westinghouse, C), Southern contractors) start of work governed by such progrincluding changes th and plant e
D.
ams.
of the qualitAudits or verifies accomplishment Westinghouse, y assurance prc grams of GPC,-of delegated audits
- SCS, BPC, or servicesand suppliers of materials, equipment, approved quality assura,nce programsto ensure compliance with-E.
and procedures.
Inspection and Enforcement, Processes correspondence rectorate of F.
Assures that site activities conf g
assurance program requirements and prorm to quality
\\t; G.
ocedures.
Assures that audit, surveillance, related functions. requirements are carried out on projand monitoring ect quality-H.
Maintains and controls the VEGP Qu li e
'q Manual.
a ty Assurance I.
Ensures the proper implementation quality surveillance functions /activitiof the supplier thereto.
es and changes 17.2.1-8 Amend. 8 7/84
d
')
VEGP-FSAR-17
.k operation and will increase to approximately 15 when Unit 2 becomes operational.
C<D' N-)The corporate quality assurance engineering / support groups 8
provide technical and administrative support to the quality assurance department in the. performance-of its assigned responsibilities.
,. m 19) 17.2.1.3.1 General Manager of Quality Assurance and Radiological Health and Safety The GMQA, located at the general office, is responsible to the executive vice president-power supply for assuring implementation of the OQAP and for managing activities of the GPC quality assurance organization.
The GMQA can effectively-E assure conformance to the quality assurance requirements and-is l8 free from undue influence and from responsibility for cost.and schedules.
The GMQA has a staff at the general office and a staff located at the site to conduct quality assurance activities.
The GMQA has been given authority by 'the executive vice presis--;-power' suppl'y to stop, in a timely manner, work on the VEGP site which is not being performed in accordance with
. -)
the provisions of the OQAP.
The GMQA keeps management _ informed on the effectiveness and implementation of the OQAP through' distribution of audit reports and other documents.
Specific duties and responsibilities of the GMQA are as follows:
A.
Manages the GPC quality assurance department.
B.
Develops.the quality assurance' portions of OQAP to conform to approved policies.
C.
Approves the GPC VEGP Quality Assurance Manual and changes thereto.
D.
Maintains close liaison with the general manager-nuclear operations to ensure that program policies and procedures are being implemented and enforced.
8 vf.g E.
Keeps the executive vice president-power supply
'W9 informed orally on routine matters, but reports significant items immediately, both orally and'in writing.
In addition, major audit reports, including summaries of audits by major contractors, are forwarded to the executive vice president.
I[j),
F.
Informs management of quality assurance activities through distribution of audit reports and other l
correspondence.
j 17.2.1-7 Amend. 8 7/84 l
VEGP-FSAR-17
.-]
17.2.1.3.3 Quality Assurance Site Manager Located at the plant site and reporting to the VEGP quality
,g) assurance manager, the quality assurance site manager manages the quality assurance field group.
17.2-.l.3.4 Quality Assurance Field Group 1
The quality assurance department personnel have written authority l8 I
to stop work on a system, structure, or component that affects-nuclear safety, if the work is not in accordance with provisions of the OQAP..
Disputes arising from differences of _
opinion between quality assurance personnel.and other department personnel will be resolved by the lowest level of management possible.
If necessary, the executive vice president will'make the final disposition.
The GMQA shall regularly ass'ess the quality. assurance department workload to ensure a sufficient number of personnel are available for complete and efficient implementation of their quality assurance department responsibilities.
Specific-duties and responsibilities of the quality' assurance field group (hcaded by the quality assurance site manager) are-as.follows:-
)
A.
Prepares annual schedule and performs planned-audits of organizations and activities (GPC and contractors).
B.-
Provides the VEGP quality assurance manager with weekly written activity reports.
C.
Maintains open-items list from NRC inspections and' quality assurance field group audits; - follows up until-resolved. and closed out.
D.
Acts as site contact with the NRC Department of Inspection and Enforcement.
,Q)
E.
The quality assurance department participates in the development process for piant procedures.
This includes comparison with Hatch Nuclear Plant procedures, commitments to enhance consistency-of overall procedure development, and assurance that appropriate' quality assurance program elements are 8
(, )
included in procedures.
Quality assurance department personnel have access to meetings where quality matters are discussed.
The VEGP quality assurance manager shall designate the types of meetings his staff or representative (s) from his staff will routinely attend,
[.")
including day-to-day work planning meetings and staff meetings.
.. /
17.2.1-9 Amend. 8 7/84
VEGP-FSAR-17 C
'a 17.2.1.4 Engineering The GPC power supply engineering and services department,_-under the direction of the vice president and chief enginear-power
- L supply engineering and services is responsible for providing engineering and technical support to the various power supply organizations.
During the operation of VEGP,-the power supply engineering and services department is responsible for the management of design engineering support, the qualification of suppliers, and the review of procurement documents for quality
(
requirements.
SCS is the architect / engineer for VEGP during operation.
The.
GPC power supply engineering and services department Vogtle project manager serves as the interface between the GPC nuclear power department and SCS for coordination and direction of engineering support provided by SCS.
In addition, SCS provides quality assurance support, including audits, supplier qualification and surveillan'ces, and engineering procedure reviews.
SCS also administers for VEGP the contract for-8 engineering services provided by BPC.
Activities within the SCS work' scope are governed by the SCS VEOP Operational Support Policy and Procedures Manual and the SCS Engineering Policy and Procedures Manual.
These procedures are reviewed'and concurred with by the SCS quality assurance organizati.on.
The GPC GMQA performs or causes to be performed audits of these functions.
BPC is under contract to SCS to provide architect / engineering services.
The work scope includes plant design, development of purchase recommendations for-equipment and materials, administration of purchase orders resulting from SCS-developed purchase recommendations such as the nuclear steam supply system, and support of the SCS supplier surveillance functions i
by providing procurement surveillance services for selected Q-list items.
Activities within the BPC work scope are governed by the BPC VEGP Nuclear Quality Assurance Department Procedures Manual and Vogtle Project Engineering Procedures Manual.
The GPC GMQA performs or causes to be performed audits of these
!([
procedures and functions.
17.2.1.5 Vogtle Project The vice president and general manager-Vogtle Project is bh responsible to the senior vice president-nuclear power for implementation of the OQAP for performing construction activities at an operating nuclear' power plant..
.w 0379V 17.2.1-10 Amend. 8 7/84
i.
^
VEGP-ESAR-17 17.2.2 OPERATIONS QUALITY ASSURANCE PROGRAM The operations quality assurance program (OQAP_) requirements
~j and controls are established to comply with the requirements of i
10 CFR 50, Appendix B and 50.5 5a, as described in the Final Safety Analysis Report.
The VEGP Quality Assurance Manual, approved by the executive vice president-power supply, ensures that the oQAP meets the criteria of 10 CFR 50, Appendix B.
The Quality Assurance Manual-specifically addresses each criterion of Appendix B and lists 8
i the key implementing plant procedures.
The Quality Assurance Manual will be updated and implementing procedures will be issued at least 90 days prior to fuel load.
The policies, goals, and objectives of the.OQAP are summarized in the introductory paragraph to section 17.2..
The ite..ns to be covered under'the OQAP are designated as "Q" items and are listed for general guidance in table 3.2.2-1.
This list is prepared and kept current by tne architect / engineer during plant design, construction, and startup, with control a
maintained by the Georgia Power Company (GPC) nuclear operations l8 department during plant operation.
The following guidance is considered when specifying quality requirements:
e The importance of malfunction or failure of the item to plant safety or reliability.
The design and fabrication complexity or uniqueness of e
the item.
The need for special controls and surveillance over o
process and equipment, The degree to which functional compliance can be e
demonstrated by inspection or test.
cw qfD e
The quality history and degree of standardization of the item.
Safety-related activities will be carried out under suitably controlled conditions,_ including use of written, approved procedures and appropriate equipment, proper environmental gl) conditions, and assurance that prerequisites have been satisfied.
Quality affecting procedures required for the administration of the OQAP are reviewed for consistency with program commitments and corporate policies and are properly documented and controlled.
These policies are documented and 8
approved by the general manager-Vogtle nuclear-operations.
)
Quality policies and procedures are mandatory requirements which Y
must be implemented and enforced.
Documented' procedures control J
17.2.2-1 Amend. 8 -7/84
VEGP-FSAR-17 i
the actions of the various organizations involved such as quality ass'urance, quality control, engineering, and operations, 8
including actions to determine the extent of: quality assurance control to be applied.
These activities include but are not i
limited to certain aspects of the following-as they. apply to-safety-related structures, equipment, and systems:
Administrative controls and reportin': requirements.
e g
i Health physics and radiation protection.
e 4
e Environmental monitoring and environmental technical specifications.
4 e
Plant chemistry.
e Radioact'.ve waste control, e
Reactor and plant operations.
Materials control (procurement, storage,-and issue),
e o
Quality control (nondestructive examination;.
inspection, etc.).
f e
Surveillance program.
4 o
Test equipment-calibration and. control.
Security Plan and procedures..
o Emergency Plan and procedures.
Design changes and plant modification control.
o I
Departmental training programs.-
e i
o Maintenance programs.
.c
. t.g Fuel handling and special nuclear material control.
e i
Inservice inspection program.
o Procedure controlland review.
o Records management and document control.
Fire protection program.(subsection 9.5.1).
e Corrective action programs.
f7 r;;
e Computer code programs.
17.2.2-2 Amend. 8 7/84
4
'. S VEGP-FSAR-17
)
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17.2.2 OPERATIONS QUALITY ASSURANCE PROGRAM The operations quality assurance program (vDAP) requirements
,]
and controls are established to comply with the requirements of 10 CFR 50, Appendix B and 50.55a, as described in the Final s.
Safety Analysis Report.
The VEGP Quality Assurance Manual, approved by the executive vice president-power supply, ensures that the OQAP meets the criteria of 10 CFR 50, Appendix B.
The Quality Assurance Manual specifically addresses each criterion of Appendix B and lists B
the key implementing plant procedures.
The Quality Assurance Manual will be updated and implementing procedures will be issued at least 90 days prior to fuel load.
The policies, goals, and objectives of the-0QAP are summarized in the introductory paragraph to section 17.2.
The items to be covered under*the OQAP are designated as "Q" items and are listed for gen.eral guidance in table 3.2.2-1.
This list is prepared and kept current by the architect / engineer during plant design, construction, and startup, with control a
maintained by the Georgia Power company (GPC) nuclear operations l8 department during plant operation.
The following guidance is
}')
considered when specifying quality requirements:
o The importance of nalfunction or failure of the item to plant safety or reliability, The design and fabrication complexity or uniqueness of o
the item, The need for special controls and surveillance over o
process and equipment.
The degree to which functional compliance can ce e
demonstrated by inspection or test.,
(f)
The quality history and degree of standardization of e
the item.
Safety-related activities will be carried out under suitably controlled conditions, including use of written, approved procedures and appropriate equipment, proper environmental r.
d.i) conditions, and assurance that prerequisites have been satisfjed, Quality affecting procedurer required for the administration of the OQAP are. reviewed for consistency with.
program commitments and corporate policies and are properly documented and controlled.
These policies are documented and-8 j
approved by the general manager-Vogtle nuclear operations.
.,f}
Quality policies and procedures are mandatory requirements which must be implemented and enforced.
Documented procedures control 17.2.2-1 Amend. 8 7/04
^
VEGP-FSAR-17
)
Measurec shall be established to ensure that major contractors performing safety-related activities at or in association with VEGP have an adequate quality assurance / quality control program commensurate with the scope of their activities.
Applicable e.
sections of American National standards Institute N18.7-1976 will be required of contractors and suppliers to the degree necessary to ensure compliance with the OQAP.
It is the responsibility of the GPC power supply engineerang n
services, purchasing department, and Southern Company Services, B B
'./
Inc., to comply with the OQAP for plant-associated activities such as procurement, qualification of suppliers, new plant design, and the necessary redesign or evaluation of any of the safety-related systems, structures, or components.
With complete support of GPC management to assist in the assignment, the general manager-Vogtle nuclear operations shall l8 have the overall site responsibility for developing and implementing the OQAP with the exceptions to controls that are assigned to the quality assurance department.
The quality assurance department conducts independent audits of quality activities as necessary to assess the ecope, status, implementation, and effectiveness of the 09AP.
These audits will be conducted in accordance with predetermined. schedules, with audit results documented in reports and a follovup system utilizedtoensurecorrectiveactionistakenwhennecessaryandl8 to verify implementation.
The general manager-quality assurance transmits the results of the audit findings to.the executive vice president-power supply.
Measures shall be provided for indoctrination and training of personnel performing safety-related activities to eneure that the individual attains quality in job performance and complies with GPC quality policies and procedures.
(Ser section 13.2 for training description.)
Quality assurance department personnel, in accordance with Q,- )
quality assurance department procedures, will receive fortaal N'
and on-the-job training in quality assurance policies, requirements, procedures, techniques, plant operation, maintenance, nonconformance control, and auditing.
These procedures also prescribe methods for documenting the accomplishments of training.
Xecords of training and qualifications of quality assurance department personnel will be maintained by the general manager-quality assurance and will document compliance with appropriate requirements.
Personnel of departments other than quality assurance, in addition to the training described in section
.]
13.2, will receive quality assurance indoctrination which includes quality assurance policies and procedures.
In 17.2.2-3 Amerd. 8 7/84
VEGP-FSAR-17 C
addition to this indoctrination, plant operators, engineering l8 maintenance personnel, quality control personnel, and health physics personnel will receive instruction in their areas of the OQAP.
The superintendent of nuclear training will schedule, evaluate, and maintain records of training and indoctrination of d
plant personnel.
Records of training programs shall include V
objectives, content of program, attendees, and date of attendance.
The quality assurance program for design and construction establishes the organization and basic controls to be applied 6
during equipment turnover, preoperational test preparation, running of the test, and review of the results.
GPC construction department personnel wil: nrovide assistance to GPC nuclear operations personnel duriny system checkout and l8 construction acceptance testing, as controlled by site procedures.
Audits will be performed by quality assurance site personnel to ensure that procedure requirements and prop 1r turnover are'being implemented.
Preoperational test procedures will be written by technical personnel familiar with the system design and will be reviewed for adequate control to ensure quality.
Test supervisors will be selected, and quality assurance instruction will be provided to these supervisors.
Fuel loading procedures will be reviewed for adequate control to ensure quality, and specified audits of the loading activities will be performed.
Startup and power ascension testing will be controlled by written test procedures, reviewed for adequate control to ensure quality; certain test requirements will have to be successfully completed, documented, and reviewed before continuing te the next test.
Audits of startup and power ascension tests will ensure these requirements are being implemented.
Chapter 14 and the VEGP Startup Manual provide additional details on these programs and requirements.
Control shall be established for turnover of responsibilities and records from the nuclear steam supply system (NSSS) vendor (Westinghouse) and the architect /enginear (Bechtel Power Corporation) to GPC.
These controla viii ensure that program (l'e requirements previously implemented by the NSSS vendor and the architect / engineer are implemented under the OQAP.
This turnover will be performed to written procedures, and appropriate audits will assure control is maintained.
Written procedures will be in effcet in sufficient time to permit review for quality requirements before actual turnover.
((
';he -OQAP requirements and controls shall be implemented at least 90 days prior to fuel load and are in effect through the operational life of the plant.
Changes that reduce commitments l8 to the OQAP will be submitted $ n writing to the Nuclear Regulatory Commission (NRC) for approval prior to implementation.
17.2.2-4 Amend. 8 7/84
4
,}
VEGP-FSAR-17 Changes to the OQAP description that do not reduce the commitments will be submitted to the NRC at least annually.
The commitments of this subsection are audited according to the B
quality assurance audit program, which is described in subsection 17.2.18.
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-3 03BOV 17.2.2-5 Amend. B 7/84
h VEGP-FFAR-17
./
17.2.3 DESIGN CHANGE CONTROL Measures are established to ensure that, for design activities
)
associated with modifications to the operating plant, g4v applicable regulatory requirements for design bases are properly translated into specifications, drawings, and procedures.
The quality assurance requirements for design l8 change control are consistent with the position of Regulatory Guide 1.64, Quality Assurance Requirements for the Design of
'g Nuclear Power Plants, as discussed in section 1.9.
Plant mana ament shall have the responsibility for controlling, v
approving, and implementing plant design modifications after turnover.
Written procedures will identify the positions or organizations responsible for design verification and define their authority and responsibility.
The plant review board shall review all proposed modifications to safety-related systems to determine whether an unreviewed safety question (10 CFR 50.59) is involved.
'Unreviewed safety questions and the safety evaluations of design changes and procedure changes for safety-related systems shall be reviewed by the safety review board.
If plant management determines that engineering assistance is required, the change request shall be forwarded to an appropriate engineering organization for evaluation.
The detailed engineering will be performed by an approved architect / engineering organization.
The responsible engineering organization including the verifier shall have
[8 access to pertinent background information, have demonstrated competence in the specific design area, and have an understanding of the requirements of the original design.
Design procedures shall be approved by the appropriate authorities before any design modifications are performed.
These procedures will also ensure that the design control is commensurate with the original design and that proper design
,3 NJ review and verification are performed.
Measures are provided to ensure that the designer is provided'with the latest revisions to drawings, specifications, and other applicable design documents.
Design changes made to VEGP are acceiplished in a planned and
';'")
controlled manner in accordance with written, approved procedures.
These procedures include provisions as necessary to ensure that:
A.
Design documents, specifications, drawings, calculations, procedures, and instructions reflect l8
. >..)
applicable regulatory requirements and design bases.
17.2.3-1 Amend. 8 7/84
VEGP-FSAR-17 e
i B.
Design documents specify quality requirements or reference quality standards as necessary.
C.
There is adequate review of suitability of materials, parts, equipment, and processes which are essential to
.E' the safety-related functions of structures, systems, and components.
l D.
Materials, parts, and equipment which are standard commercial (off tS.o shelf) or which have been previously approved for a different application are f'
evaluated for suitability prior to selection.
E.
Design documents and plant procedures are revised to reflect design modifications.
F.
Internal and external design interfaces between organizations participating in design modifications are adequately controlled. including the review, approval, release, and distribution of design documents and revisions.
These controls ensure that structures, systems, and components are compatible a
geometrically, functionally, and with processes and the environment.
C.
Computer codes used for design computation are verified and certified for their intended use.
The above controls are applied as necessary to such aspects of design as reactor physics, seismic stress, thermal, hydraulic, radiation, and accident analyses; compatibility of materials; and accessibility for inservice inspection, maintenance, and repair.
The adequacy of design changes shall be verified by the performance of design reviews, alternate calcule.tions, or qualification testing.
The control measures specified herein for control of design verification activities are as follows:
E A.
Personnel responsible for design verification do not include the original designer.
Verification may be performed by the same organization responsible for the original design change, B.
Written procedures identify the positions or kI e
organizations responsible for design verification and
~
define their authority and responsibility.
In addition, procedures will identify the verifier responsibilities, the area to be verified, the 8
pertinent considerations to be verified, and the extent of documentation.
.c C
17.2.3-2 Amend. 8 7/84
1
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VEGP-FSAR-17 c.
Qualification tests to verify the adequacy of design are performed as applicable using the most adverse specified design conditions practical to provide or b,j
- simulate, 2
D.
Design changes are reviewed to ensure that design criteria are defined and that inspection and test criteria are identified.
E.
New or innovative designs will be subjected to comprehensive design review, which may include calculational checks or a testing program under adverse design conditions.
F.
Written procedures will require a documented check to verify the dimensional accuracy and completeness of design drawings and specifications.
G.
Desig6 verification; if other than by qualification testing of a prototype or lead production unit, is completed prior to release for procurement,.
manufacturing, and installation or to another organization for use in other design activities.
In those cases where this timing cannot be met, the design i
verification may be deferred, pros.. ding that the justification for this action is documented and that a
the unverified portion of the design output document and all design output documents, based on-the unverified data, are appropriately identified and controlled.
In all cases, verification is completed prior to relying upon the item to perform its function.
There is a comprehensive audit system to verify that the design control system maintained by the responsible organizations I
during the operation of the VECP is adequate and functioning properly.
If)
Any errors or deficiencies found in the design process or the design itself are documented and corrective action taken as described in subsection 17.2.16.
Design documents and revisions thereto are controlled and distributed as described in subsection 17.2.6.
Records of tW) design activities and design changes are collected, stored, and maintained in a systematic manner to prevent inadvertent use of superseded documents.
1 VEGP plant procedures will require that plant personnel are made i
l aware of design changes / modifications which may affect the
![s) performance of their duties.
Methods by which plant personnel 8
are made aware will include procedure revision training, night orders, and structured training for major modifications.,
17.2.3-3 Amend. 8 7/84
VEGP-FSAR-17 Compliance with design control commitments is ensured by the quality assurance audit program, which is described in 8
subsection 17.2.18.
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l 0381V 17.2.3-4 Amend. 8 7/84
3 VEOP-FSAR-17
.)
17.2.4 PFOCUREMENT DOCUMENT CONTROL The quality requirements for the control of documents prepared by Georgia Power company or its designated agents, for safety-s
)
related components, materials, and services are consistent with the provisions of Regulatory Guide 1.123, Quality Ascurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants, as described in section 1.9.
The vice president and general manager-nuclear operations is responsible
']
f or procuretnent planning of VEGP.
To satisfy the quality assurance requirements for procurement document control, the following specific requirements shall be implemented.
Measures shall be established to ensure:
A.
Procedures are established delineating the cequence of actions to be accomplished in the preparation, review, approval, and control of procurement documents.
The general manager-Vogtle nuclear operations, in conjunction with the vice president-engineering and 8
services, is responsible for the preparation, review, approval, and control of procurement documents.
B.
A review and concurrence of the adequacy of quality assurance requirements stated in procurement documents is performed by qualified personnel knowledgeable in the quality assurance requirements.
Plant procedures will define training requirements for ensuring knowledge of quality assurance requirements.
This review is to determine that all quality assurance requirements are correctly stated, can be inspected and controlled, and provide adequate acceptance and rejection criteria and that the procurement document has been prepared in accordance with quality assurance program requirements.
C.
The person performit? the review will be an individual
((')
independent of the peocurement document originator.
Documented evidence of the review and approval of procurement documents is provided and available for verification.
D.
Procurement documents identify those 10 CFR 50, cp)
Appendix B, requirements that must be complied with and described in the supplier's quality assurance program.
This quality assurance program or portions thereof shall be reviewed and concurred with by the general manager-Vogtle nuclear operations, in conjunction with the vice president-engineering and B
.a; services, and qualified personnel knowledgeable e
17.2.4-1 Amend. 8 7/84
1 i
VEOP-FSAR-17 4
g; l-An quality assurance prior-to implementation of l
activities affected by the program.
E.
Procurement documents contain or reference applicable-design basis technical requirements including-
'%(
t i
regulatory requirements, component and material identification, drawings, specifications, codes and industrial standards, including their. revision status, test and inspection requirements, and special-process instructions, for activities such as. fabrication,
..c cleaning, erecting, packaging, handling, shipping, storing, and inspecting.
i F.
Procurement documents contain applicablearequirements which identify the documentation to be prepared, maintained,. submitted, and made available to.the h
general manager-Vogtle nuclear operations for review g8 and/or approval, such as drawings, specifications, procedures, inspection and-fabrication plans, inspection and test records, personnel and procedure-3 qualifications, materials, and chemical and physical test results.
E 0.
Procurement documents contain the requirements for:the retention, control, and_ maintenance:of vendor records.
H.
Procurement documents contain_the procuring agency's right of access to vendor's facilities and records-for-... -
source inspection and audit.
Changes and/or revisions to procurement documents are 4
subject to the same review,and approval requirements as the original documents.
J.
Procurement documents for: spare or replacement parts of safety-related structures, systems, and' components-are reviewed for adequacy by qualified: personnel.
knowledgeable in quality assuranceLrequirements.
The (GE review is to determine similarity, compatibility,.and
-6 inclusion of the quality assurance requirements-and 30 acceptance criteria of the' original item.
Assurance that the requirements for procurement document control are implemented will be provided by.the audit program-(M,'
describedLin. subsection 17.2.18.-
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'N 0382V 17.2.4-2
.Anend.L8 -7/84
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"I 17.2.5 INSTRUCTIONS, PROCEDURES, AND DRAWINGS Activities affecting quality shall be prescribed by and s
li gr, accomplished in accordance with documented instructions, procedures, or drawings.
The general manager-Vogtle nuclear
[. %C r,,
operations is responsible for ensuring that procedures are g
prepared and followed and that personnel are trained on the
?>
procedures.
They shall contain appropriate quantitative (such as dimensions, tolerances, and operating limits) or qualitative (such as workmenship and samples) acceptance criteria for 13 eNI determining that important activities have been satisfactorily 1
,??
accomplished.
The requirements dealing with instructions,
<j procedures, or drawings are consistent with the provisions of
)
Regulatory Guide 1.30, Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and 4
,g i,
Electric Equipment; Regulatory Guide 1.33, Quality Assurance l;
Program Requirements (Operation); and Regulatory Guide 1.116, Quality Assurance Requirements for Installation, Inspection, and
-J Testing of Mechanical Equipment and Services, as described in section 1.9.
17.2.5.1 Plant Procedures, Instruction, and Drawings
(
The VEGP procedure manuals will contain procedures which shall
'i be used for periodic tests and calibrations, special processes, modifications, maintenance, and other plant activities on safety-related systems, equipment, or structures.
Certain
.y
- lit procedures important to safety shall be reviewed by the plant review board before being signed by a member of plant
,J management.
Inspection plans, t-e s t s, calibrations, special processes, maintenance, modifications, repair procedures, and
.'O ;
changes thereto will be reviewed and concurred with by a person s
h knowledgeable in quality assurance requirements.
Plant
' :];j procedures will define training requirements for ensuring
' J.}
knowledge of quality assurance requirements.
3y {h Written administrative procedures will ensure proper control of instructions such as temporary procedure changes and standing
- i N
orders.
These instructions will be of limited scope and will y
- '.]
be issued for limited time periods to ensure proper
. b.
requirements, included in the procedures, are not bypassed or t
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neglected, VQ
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.9 Plant drawings will reflect the properly reviewed and approved
'dt configuration of the plant, Changes will be as a result of design changes (subsection 17.2.3.)
or "as-builts" which will
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be controlled by written procedures the same as drawings until 7/f properly revised drawings are received.
The design m'- Ll (N-organization will implement design and drawing control on 4
(
design documents through written procedures.
17.2.5-1 Amend. B 7/84 L
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VEGP-FSAR-17
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'17. 2.5.2 other Procedures
' ' 3.
Each contractor performing quality-related activities shall
'j have properly reviewed and approved quality assurance programs-
,i or procedures or function under the control of the operations
' f t,,'
quality assurknee-program.
These programs or procedures shall-A be reviewed to ensure that they meet the quality assurance l8
']
requirements-contained herein.
- [h Confirmation that these instructions and procedures are l
~4 properly implemented is accomplished through activities
'f; performed by the quality assurance-organization.
See
- w subsection 17.2.18 for details.
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0383V 7.2.5 Amend. 8-7/84:
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VEGP-FSAR-17 17.2.6 DOCUMENT CONTROL Herein are contained the requirements for the control of documents that prescribe activities affecting quality._ The o}
docoments which are to be controlled include
.s 1
A.
Manufacturing, design, construction, and-installation drawings for safety-related structures, systems, or components.
'.. )
Approved procurement documents for safety-related
~J B.
structures, systems, or components.
C.
Plant procedures which implement requirements of the operations quality assurance program.
D.
Maintenance, modification, and operating procedures which implement requirements of the operations quality assurance program.
E.
Final Safety Analysis Report, Emergency Plan, Security Plan, environmental reports, Technical Specifications, and operating License Stage Environmental Report.
1 F.
Inspection and test procedures.for safety-related structures, systems, or components.
G.
Design documents (e.g.,
calculations, specifications, and analyses) including documents related to computer codes.
H.
Instructions and procedures for such activities as 8
l fabrication and installation.
1.
As-built documents.
J.
Quality assurance and quality control manuals.
K.
Deficiency-reports.
The requirements for document control are consistent with the position of Regulatory Guide 1.33, Quality. Assurance Program Requirements (Operation), as described in section 1.9.
,e.s Provisions are included which require-that:
gj)
A.
Documents and changes thereto are reviewed for adequacy and approved for release by authorized personnel in accordance with written procedures.
These procedures identify those positions responsible
. ((;s}
for reviewing, aoproving, and issuing documents and~
revisions thereto.
Measures-are also established to
. 17.2.6-1
. Amend. 8 7/84-
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1 VEGP-FSAR-17 review documents prior to release to ensure that the quality assurance requirements are sufficiently, clearly, and accurately stated.
The individuals responsible for the quality assurance requirement review shall be an individual other than the person who b
generated the document.
Individuals authorized to 8
per form the quality assurance requirement review shall be knowledgeable of the quality assurance requirements.
The approving authority is responsible for implementing review of the document for quality assurance requirements.
B.
Documents and changes thereto are promptly distributed to ensure availability prior to commencement of work.
"As-built" documents are prepared ir a timely manner to aceurately reflect the actual plant design.
C.
Changes to documents are reviewed and approved by the name' organization that performed the original review and approval unless~another qualified organization is designated.
D.
Master status lists identifying the current revision of documents are periodically updated and utilized to preclude the use of superseded documents.
Procedures are established for control of document revision.
These procedures will specify the types of documents to B
be controlled and the periodic updating and distribution of controlled documents.
E.
Obsolete or superseded documents are destroyed or identified to prevent their inadvertent use.
The superintendent of administration is responsible to plant management for ensuring that plant personnel are provided with current documents.
The responsible supervisors are responsible for ensuring that the latest revision of appropriate documents is being used to perform safety-related activities.
Documents controlled by offrite organizations will receive control kg comparable to that of site documents.
The quality assurance department will audit activities to determine proper implementation of the quality requirements contained herein.
The quality assurance audit function is
,e described in subsection 17.2.18.
it i.-~
0384V 17.2.6-2 Amend. 8 7/84
s VEGP-FSAR-17
)
c.
17.2.7 CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES Spare and replacement parts of safety-related structures,
.,'}
systems, and components are subject to quality assurance program controls in place when the procurement is made and to technical requirements that comply with Final Safety Analysis Report 8
requirements.
Expendable or consumable items will be procured in accordance with the provision described herein.
The requirements for the control of purchased materials, equipment,
~ ;)
and services are consistent with the positions of Regulatory Guide 1.30, Quality Assurance Requirements for Packing, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants, and Regulatory Guide 1.123, Quality Assurance Requirements for Control of Procuroment of Items and Survices for Nuclear Power Plants, as described in nection 1.9.
17.2.7.1 Supplier Qualification The vice president and general manager-nuclear operations is responsible for ensuring qualification of suppliers of safety-related equipment, materials, or services, including B
spare and replacement parts, for the VEOP.
These activities are in accordance with the operations quality assurance program.
Georgia Power Company (GPC) shall review the effectiveness of quality control of approved suppliers or subsuppliers at intervals designed to maintain confidence in the suppliers' The review intervals shall be determined according to
- programs, the complexity of the product or services received from these suppliers.
These reviews will also include periodically evaluating the suppliers' certificates of conformance by audits, independent inspections, or tests to ensure they are valid.
Prior to accepting a prospective supplier as a qualified GPC nuclear supplier, qualified personnel will evaluate the prospective supplier's capability to provide services or products of acceptable quality based on one or more of the
.,3 Q'33 following:
A.
The supplier's capability to comply with the elements of 10 CFR 50, Appendix B, that are applicable to the type of material, equipment, or services being procured.
k" B.
A review of previous records and performance of suppliers who have provided similar articles of the type being procured.
C.
A survey of the supplier's facilities and quality
'1.)
assurance program to determine the capability to E-supply a product which meets the design, manufacturing, 17.2.7 Amend. 8 7/84
VEGP-FSAR-17 and quality assurance requirements.
If a survey is performed, the results wjll be documented and filed.
The method used and information analyzed to qualify a supplier will also be documented.
Where surveys or audits cannot be conducted, acceptable b
alternativen will be provided.
Plant procedures will require that procurement documents specify:
A.
Documentation that identifies the purchased item and l8 7
the specific procurement requirements (e.g., codes, standards, and specifications) met by the item.
B.
Documentation identifying any procurement requirements that have not been met.
C.
A description of those nonconformances from the procurement requirements dispositioned " accept as is" or " repair."
17.2.7.2 Evaluation Process The evaluation of suppliers, including spare and replacement parts for safety-related systems and surveillance during fabrication, inspection, testing, and shipment, shall be performed in accordance with procedurec established by the vice l
president and general manager-nuclear operations.
These lg procedures shall include the tollowing:
A.
Instructions that specify the characteristics or
. processes to be witnessed, inspected or verified, and accepted; the method of surveillance and the extent of documentation required; and those responsible for implementing these instructions and releasing i
documentation.
B.
Audits and surveillance which enrure that the supplier
//
complies with the quality requirements.
Surveillance i-shall be performed on those items where verification of procurement requirements cannot be determined upon receipt.
17.2.7.3 Receiving Inspection Receipt inspections at VEGP are performed in accordance with written procedures to ensure that:
A.
Materials, equipment, or components are properly identified and traceable to associated documentation.
17.2.7-2 Amend. 8 7/84
hT.3 VEOP-FSAR-17
)
Review of documentation required by the purchase order l8 is performed by quality control.
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B.
Inspections, tests, and other specified records
's attesting to the acceptance of materials, equipment, and components are completed and available at VEGP prior to installation or use.
C.
Mater'ials, equipment, and components are inspected and
, f.}
judged acceptable in accordance with predetermined inspection instructions _ prior to installation or use.
Items accepted and_ released are identified as to their inspection status prior to forwarding them to a controlled s'corage area or releasing them for installation or. further work.
8 Nonconforming' items are clearly identified, controlled, and segregated where practical,~until proper disposition is made.
For commercial (off the shelf) items where specific quality assurance controls appropriate-for nuclear applications cannot be imposed in a practical manner, special quality verification
, _i requirements shall be established to provide the necessary assurance of the item.
The quality assurance department will audit the control of purchased materitls, equipment, and services to ensure proper-implementation of the requirements.
See subsection l'.2.18 for 7
a description of the quality assurance audit system.
l k
0385V 17.2.7-3 Amend. 8 7/84 i
i i
VEGP-FSAR-17 a:)
17.2.8 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS, AND COMPONENTS 8
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The quality assurance requirements for the identification and-control of safety-related materials, parts, and components, a
including spare or replacement parts, are consistent with the s
position of Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation), and Regulatory Guide 1.38, Quality Assurance Requirements for Packing, Shipping, Receiving,
")
Storage, and Handling of Items for Water-Cooled Nuclear Power Plants, as described in section 1.9.
Materials, parts, and components will be identified and l
controlled to prevent the use of incorrect or defective items.
l The location and method of identification shall not affect the quality or the function of the item.
Procedures imp' lementing requirements for the identification and f
control of materials-(including consumables), parts, and componente provide for the following e
A.
Verification that the items received at VEGP are properly ider.tified and can be traced to the 3
appropriate documentation, such as drawings, specifications, purchase orders, manufacturing and inspection documents, nonconformance reports, or mill test reports, or-can be identified-by a manufacturer's catalog.
B.
Verification of item identification consistent with the inventory control system and traceable to documentation which identifies the proper uses or applications of the item.
The plant staff is responsible-for the identification and control of materials, parts, and components =which.are-received, stored, installed, and used at VEGP.
The quality control 8
(*_f) department, which is responsible for receipt inspection,-and warehouse personnel, who are responsible for storing and releasing items, ensures the verification-and documentation-of-l correct item identification. prior to release for fabricatAon,.
casembly, shipment, and installation. = Plant administrative 1
procedures shall describe plant staff activities and j
[,j) responsibilities for identifying and controlling this equipment, i
'1 The quality assurance department will audit the above activities.
See subsection 17.2.18 for description of audit activities.
i 0386V 17.2.8-1 Amend. 8 7/84
J VEOP-FSAR-17 17.2.9 CONTROL OF SPECIAL PROCESSES The requirements for the control of special processes, which
.. /4 are those processes where direct inspection is impossible or G) disadvantageous, such as welding, heat treating, nondestructive 3-testing, brazing, chemical cleaning, electroplating, and g
protective _ coating, are consistent with the. position of Regulatory Guide 1.30, Quality Assurance Requirements for the Installation, Inspection, and Testing of' Instrumentation and 7)
Electric Equipment; Regulatory Guide 1,37, Quality Assurance -
Requirements.for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power. Plants; and Regulatory Guide 1.58, Qualification-of Nuclear Power Plant Inspection, Examination, and Testing Personnel, as described in section 1.9.
Activities dealing with special processes shall-be performed by.
qualified per'sonnel using proper equipment and in-accordance with written, ' approved procedures.
.These personnel and procedures will be qualified in accordance with the applicable code requirements.
These qualifications, along with the approved procedures,.matertal specifications,.and other quality assurance documents, including verification,.are available.in
,')
the plant documentation file.
Qualification-of special-processes, equipment,.and personnel is the responsibility of the superintendents and supervisors for activities under their purview.
Qualified test laboratories.
t and consultants may be used in qualification of special L
processes.
Procedures shall be developed which delineate the i
requirements for special processes.
These procedures will i
specify the responsibilities of the quality control department-for control of the special processes through the use of inspection hold p'oints-and the performance of nondestructive 8
testing.
These procedures will. ensure-recording acceptable accomplishment of special processes us. evidence of ing qualified procedures and personnel and suitable and controlled equipment.
Audits of special. processes,: persorael qualifications, procedures, and records will be performed as described in subsection 17.2.18.
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VEGP-TSAR-17 17.2.10 INSPECTIONS A quality control inspection program to verify conformance of
,,, )
activities affecting quality shall be implemented at VEGP.
The requirements of this program shall be consistent with the 1-position of Regulatory Guide 1.30, Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment Regulatory cuide 1.58, Qualifications of Nuclear Power Plant-Inspection, Examination,
)
and Testing Personnel; and Regulatory Guide 1.116, Quality Assurance Requirements for Installation, Inspection,=and Testing of Mechanical Equipment and Systems,=as described in d
j section 1.9.
Inspection activities shall be performed to identify quality problems for safety-related work activities during the operation 8
3 phase of VEOP.as applicable.
If inspection.of an item or work q
operation is impossible or disadvantageous and it is necessary-to ensure its quality, indirect control by inprocess monitoring i
of the work will be performed.
Both inspection of work products and inprocess monitoring of the work will be performed when control is inadequate without both.
I nspec tior, ' at VEGP will be performed in accordance with written, approved procedures, instructions, or checklists and shall contain requirements for maintaining the fol1 wing 9
records:
4 A.
Identification of characteristics and activities to be inspected.
B.
Description of the methed of inspection.
C.
Inspcetor or data recorder identification.
D.
Acceptance and rejection criteria.
4 h])
E.
Identification of any required procedures, drawings, or specifications.
F.
Date and results of inspection..
4,r)-
Evidence of' acceptability of results.
G.
H.
Information related to conditions; adverse to quality.
I.
Action taken to resolve any discrepancy noted.
Plant. procedures require that approved calibrated test 1
L 1,y) equipment be used for tests or inspections of safety-related equipment or systems.
The accuracy requirements of inspection 17.2.10-1 Amend. 8-7/84 I
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VEGP-FSAR-17 g
4 and test equipment and the criteria for determining when a test or inspection is to be performed are contained in the established plant procedures.
The quality control supervisor.4 s responsible to plant k
management for administering and implementing tests and inspections assigned to the quality control department.
He is also responsible for analyzing the results of applicable inspections performed at VEGP.
Inspections are performed by quality control specialists (qualifications discussed in g
subsection 13.1.3) who are independent of the individuals q,
performing the activity being inspected.
Plant management ensures that quality control specialists and any other personnel performing inspection activities are qualified, and qualification records are documented and kept current.
The 8
training and qualification of these personnel will be verified I
through written examinations, proficiency testing, or oral examination.. Documented evidence of qualification for these personnel wil1 indicate the. function which the individual is qualified to perform.
Proficiency of these personnel is maintained by retraining and reexamining in accordance with applicable codes, standards, and/or procedures.
The criteria for determining the size of the quality control organization is based on known or anticipated te.sks which require quality control inspection and other functions based on experience gained at Hatch Nuclear Plant.
The approximate number of technical personnel planned for the quality control organization during normal plant operation is 25, which may be augmented by contractor personnel during outages.
The quality control supervisor and quality control specialists have written stop-work authority, including the authority to prevent equipment or systems from being returned to service if the activity was not performed in accordance with an approved procedure, specification, or drawing.
If specified inspection hold points / witness points, requiring witnessing or inspecting by an inspector and beyond which work is not to proceed without 6
inspector approval, are necessary, the specific hold points will t
be indicated in the work procedure.
If at these checkpoints the activity is found to be unsatisfactory, further processing of the activity is suspended until the problem is resolved.
Procedures requiring inspection criteria will be reviewed by qualified personnel from quality control prior to performance of F(tu the work.
This review will include a check-for the need for inspection, identification of inspection pe sonnel, and documentation of inspection results.
Further, this review will ensure that inspection requirements, methods, and acceptance criteria have been identified.
Quality control involvement in day-to-day work planning meetings and staff meetings should-r g
17.2.10-2 Amend, 8 7/84
4 VEOP-FSAR-17
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identify procedures issued for safety-related work which have not had inspection criteria included.
_ 7)
The quality assurance audit system, described in subsection 17.2.18, ensures that the foregoing requirements are implemented.
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i 0388V 17.2.10-3 Amend. 8 7/84
VEGP-FSAR-17 M.s 17.2.11 TEST CONTROL Appropriate tests are conducted and documented to ensure
,.r) satisfactory performance of structures, systems, and
.l-components.
Plant management is responsible for the conduct of plant tests and will ensure that the plant personnel adhere to the written, approved procedures.
Safety-related tests, surveillance tests, testing following modifications, receiving inspection tests, and tests of special equipment are consistent-
'n with the positions of Regulatory Guide 1.30, Quality Assurance Requirements for the Installation, Inspection, and Testing ~of Instrumentation and Electric Equipment;-Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation); Regulatory Guide 1.58, Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel; and Regulatory Guide 1.116, Quality Assurance Requirements for Installation,-Inspection, and Testing of Mechanical Equipment and Systems, as described in section 1.9.
Test procedures shall include the following where applicable:
A.
The requirements and acceptance limits contained in applicable procurement documents.
B.
Instructions for performing the test.
C.
Test prerequisites such as:
1.
Calibrated instrumentation.
2.
Adequate and appropriate equipment.-
3.
Trained, qualified, or licensed personnel when regyired.
4.
Preparation, condition, and completeness of item to be tested.
(ih 5.
Suitable and, if required, controlled environmental conditions.
6 Provisions'for_ data collection and storage.
7.
Specified_ inspection' hold points for witness by
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quality control specialists.
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8.
Acceptance and rejection criteria.
9.
Methods of documentinglor recording test data and
- results,
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10.
Verification ~ chat prerequisites are met.
l8-4 17.2.11-1_
Amend. 8 7/84-
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Changes to test procedures will receive review and approval l
equivalent to that given in the original-procedures.
Departures from approved test procedures will be permitted only under controlled conditions where the intent of the procedure I
is not changed.
Test records shall contain the following
- U S$
information:
A.
A description of the type of observation.
4 B.
Evidence of completing and verifying the test operation.
t,(
C.
A statement on reason for departure, if-applicable, D.
The date and results of the test.
E.
Information related to nonconformances, i
F.
Iden'tification of the person performing the test.
G.
A statement of the acceptability of the results.
H.
Action taken to resolve any discrepancies noted.
Test results will be recorded, reviewed, evaluated, and approved I
by the appropriate plant department supervisors, superintendents, and/or the plant review board, as appropriate.
8 Tests performed at a supplier's f acility will be controlled by procedures.
The quality assurance department will audit the above activities to verify that the testing program requirements are satisfied.
The quality assurance audit program is described in subsection
-17.2.18.
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17-.2.11-2 Amend. 8 7/84
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17.2.12 CONTROL OF MEASURING AND T2ST EQUIPMENT Measures for the control of measuring and test equipment are
,3 consistent with the position of Regulatory Guide 1.33, Quality J
Assurance Program Requirements (Operation), as described in section 1.9.
Provisions for the control of applicable measuring and test equipment require thatt
)
A.
Procedures shall be established which describe the calibration technique, calibration frequency, maintenance and control of measuring and test instruments, tools, gauges, fixtures, reference standards, transfer standards, and nondestructive test equipment to be used in the measurement and inspection of safety-related components, systems, and structures.
B.
Measurement and test equipment shall be uniquely identified and have traceability to calibration test data.
C.
Measuring and test instruments shall be calibrated and
')
maintained at specific intervals, based on the required accuracy, purpose, degree of usage, stability characteristics, and other conditions affecting the measurement.
D.
Measuring and test equipment shall be calibrated on or before the designated due date.
E.
When measuring and test equipment is found to be out of calibration, an investigation shall be conducted and documented to determine the validity of previoue inspections performed and the acceptability of tnose items previously inspected.
Procedures are established to ensure that measurements made with measuring and (ii) test equipment found to be out of calibration will be evaluated to determine the need for reinspection.
F.
Calibrating in.struments shall have known, valid relationships to a nationally recognized standard.
If no national standard exists, the basis of calibration
.,)
will be documented and approved by the responsible
~
department superintendent or a higher level of g
management.
G.
Records will be maintained which indicate the complete 3
status of all items under the calibration system and
,,1 Amend. 7 5/84 17.2.12-1 Amend. 8 7/84 1
VEGP-FSAR-17 i
)
l reflect the last and future calibration dates or the last calibration date and frequency, if applicable.
H.
Calibration facilities used for calibrating sensitive-
/
and close tolerance measuring and test equipment shall provide an environment _that is sufficiently controlled to allow the measuring device to be evaluated and calibrated to its required accuracy.
Reference standards will have an uncertainty.(error) requirement e
of no more than one-fourth of the tolerance-of the measuring and test equipment being calibrated;_a greater uncertainty will be acceptable when limited by the state of_the art. _ Equipment and standards not meeting this requirement will be documented and approved by the responsible department superintendent or by a higher level of management.
Comparison standards used in.
calibration of reference standards will have a tolerance smaller than the reference standard and will be traceable to'the standards housed in the National' Bureau of Standards.and 4
supported by certification reports and data sheets, g
The superintendent of maintenanco is responsible to the general manager-Vogtle nuclear operations for developing, approving, and-implementing precedures and instructions to establish a control and calibration program.
'He also-approves-calibration procedures.
The ad.ninistrativo procedures that control the calibration program are reviewed by the plant review board.and approved by the general manager-Vogtle nuclear operations.
The quality control department is responsible for' certifying the control of measuring and test equipment-for compliance to plant-procedures.
Quality control will verify control of measuring and test equipment d' uring inspections of work ' activities.-
i Effectiveness of the program is ensured-through periodic audits performed under the quality assurance audit system that is described in subsection 17.2.18.
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0390V 17.2.12-2 _
Amend. 7.
5/84 Amend 8-7/84
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17.2.13 HANDLING, STORING, AND SHIPPING Requirements for the control, handling, storing, shipping, cleaning, and preservation-of materials and. equipment g,g/
accordance with established instructions, procedures,,is in s
or drawings.
These requirements are consistent with provisions of Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation), and Regulatory Guide 1.38, Quality Assurance Requirements for Packing, Shipping, Receiving, Storage, and gpy)
Handling of Iten.s for Water-Cooled Nuclear Power Plants, as
- v..
described in section 1.9.
Measures prescribed by the program and associated procedures. include the following provisions:
8 A.
Inspection of items by quality control and-warehouse i
personnel will be made prior to use at the plant site, and routine surveillance will be made-during storage.
B.
For critical, sensitive, perishable, or high value items; specific written procedures for handling, storing, packing, shipping, and preserving'are used.-
These procedures reflect design and specification requirements'such as inert gas atmosphere, specific moisture content levels, and temperature-levels and i
also reflect manufacturers' recommendations in regard to special handling and storage requiremen'ts, such as shelf life and environmental controls. -Personne1' responsible for handling these items are qualified.-
C.
Special handling tools and equipment are inspected and tested in accordance with written procedures to verify.
that they are adequately maintained.
8 1
These requirements will be implemented in accordance' with approved plant procedures.
The quality assurance department will audit the above program requirements:to. verify-proper implementation.
The quality' assurance audit program is 1
described in subsection 17.2.18.
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17.2.14 INSFECTION, TESTING, AND OPERATING STATUS The requirements for identification and control of the (i C, inspection, test, and operating status of safety-related
'y;, w structures, systems, and components are consistent with the
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position of Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation), as discussed in section 1.9.
Provisions for the inspection, test, and operating status of
{,h, safety-related structures, syntems, and components require thats i
'1 i
A.
Procedures shall be established to control the use of welding stamps and inspection / status indicators, l
including the authority for application and removal of tags, markings, and labels.
i B.
Measures to preclude bypassing of required 8
inspections, tests, and other critical operations are controlled through documented procedures.
Procedures shall be established to control altering the sequence of safety-related tests, inspections, and other critical operations such that the alterations are
{_,
subject to the same control as the original.
C.
Procedures shall be established and documented to
.gj identify the inspection, test, and operating status of i
structures, systems, and components which pr. ovide i
means for ensuring that reo ed inspections and tests
,'r performed are known throug manufacturing, 6l installation, and operation.
@nj D.
The status of nonconforming, inoperative, or j
malfunctioning structures, systems, or components is clearly identified to prevent inadvertent use.
Plant management shall ensure that appropriate plant and
( j.
contractor personnel at VEGP are instructed regarding the
,3
..j purpose of, and precautions associated with, the various tags 10 and labels used at VEGP.
Control of nonconforming, 4
inoperative, or malfunctioning equipment shall be maintained to j
prevent inadvertent use that could affect plant safety.
"k (fk Effectiveness of the above requirements is ensured through
~
periodic audits performed by the quality pssurance department.
vi The quality assurance audit system is described in subsection l
- )
17.2.18.
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s 0392V 17.2e 14-1 Amend. 8 7/84
VEGP-FSAR-17 (3.-
HON 00NFORMING MATERIALS,-PARTS, OR COMPONENTS 17.2.15 Requirements for the control of nonconforming materials, ' parts, or components are consistent with the position of Regulatory
, ('j)
Guide 1.33, Quality Assurance Program Requirements (Operation);'
Regulatory Guide 1.38, Quality Assurance Requirements for
- t. '
and Handling of Items i
Packing, Shipping, Receiving, Storage; and Regulatory Guide-for Water-Cooled Nuclear Power Plants; Quality Assurance Requirements for Controlrof i
1.123, Procurement of Items and Services for Nuclear Power P.lants, as-Georgia-Power Compmc, and its j dh described in section 1.9.
contractors follow written requirements-to identify,. document, MF segregate, dispcsition, and report to the<affected organization' deviation, or other conditions-adversely any nonconformance, Provisions for controlLof nonconforming affecting quality.
materials, parts, or components require that:
Measures and procedures shall be', established to A.
control the identification, documentation,-
segregation, revicw, disposition, and notification of the affected organization.of-nonconformance-of-l8 materials, parts, components, computer _ codes; or.
services.
C.w Documentation shall be provided which clearly B.
identifies the nonconforming item, describes the nonconformance and disposition of the_nonconformance I
inspection requirements, and includes signature a
approval of the disposition.
,'P parts or components which fail-to meet Materials, C.
tequirements are identified through the use of a QM These reports, prepared by the deficiency report.
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individual icenti-fying the deficiency,_are logged end j
processed by the supervisor.of quality contret after it '
being reviewed by the shif t supervisor f:a Ang-operability implications and immediate. rep,.
The superv3sor of qualityLcontrol is (j.
requirements.
responsible for controlling =the' item through tagging or 8
segregation And by appropriate-documentation to prevent 1
7 its inadvertent installation or_use in the plant.
,'M XJ These reports are reviewed by appropriate operationsi
,j D.
and engineering-personnel and'by the plant review,bcard
., g,j(h for regulatory reportabilityLand to ensure,that appropriate corrective-action is being taken.-
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Nonconforming items are segregated from other j
E.
acceptable items (where feasible) and uniquely ioentified as nonconforming =until properly
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S dispositioned.
Items that are unique, identified, 1
17.2.'15-1
' mend.:8.7/84 J
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ci properly marked, and have their own specified storage-location need not be segregated.
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Items which require rework, repair, or replacement are inspected and tested in accordance with the original is Ju inepection and testing requirements or acceptable i,Q alternatives, as determined: by the superintendent of regulator compliance.
Rework, repair, and, associated
[yM inspection and testing at the suppliers' facilities are ny performed according to documented procedures, the D
disposition is documented, and the documentation is wj fr,rwarded to the plant site with the hardware..
- <t'.]
G.
lionec-Carmances which are dispositioned-" accept
'6, as is" or " repair" are made part.of the quality-verification records associated with the item.
E.
Deficiency reports are analyzed for-trends 1by the
~
superintendent of regulatory compliance.- Handling of these trends is discussed in' subsection 17.2.16.
I.
VEGP procedures provide assurance that deficiencies are resolved prior to the initiation of. functional tests.
Deficiencies will be evaluated to determine whether
~
they would adversely affect.the functional test.
IV.
Approved procedures protide provisions for an' independent 3dh9 review of nonconformances.
The-quality assurance audit system
';l (subsection 17.2.18) will verify compliance of each activity with the operations quality assurance program, i
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VEGP-FSAR-17 17.2.16 CORRECTIVE ACTION Approved plant procedures shall be written to ensure that
'}
conditions adverse to quality, failures, malfunctions, deficiencies, deviations, defective materials and equipment, and nonconformances on safety-related systems are promptly identified, documented, and corrected.
The program described herein requires the identification and corrective action of conditions adverse to quality.
These requirements are consistent with the provisions of Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation), as described in section 1.9.
Corrective action is initiated following the determination of conditions adverse to quality.
_ Failures, malfunctions, deficiencies, deviations, defective materials and equipment, and nonconformanc.e on safety-related systems are documented b'/-
appropriate procedures.
Various processes are used to identify problems requiring corrective action.
Items requiring prompt evaluation and correction are handled with a deficiency. report.
This process is used for nonconforming items as discussed in. subsection 17.2.15 and for other conditions adverse to quality, such as operational deficiencies, unusual events or conditions, failures to meet Technical Specifications requirements.
Other processes for identifying problems include quality assurance audits and ~
Nuclear Regulatory Commission (NRC)' inspections.
8 The superintendent egulatory compliance is responsible for coordinating the i,
,cigation of the problem to determine tdue root cause and for coordinating and tracking the necessary immediate and long term corrective action.
The superintendent of regulatory compliance is responsible for l
analyzing deficiency reports for adverse trends.
Any identified trends are reported to the-appropriate department for corrective (fp) action and to the general manager-Vogtle nuclear operations and quality assurance site manager.
The quality assurance site manager analyzes quality assurance and NRC items for adverse trends and forwards any identified _ trends to the general manager-Vogtle nuclear operations, who is responsible for-gs assessing these trends.
Baeed on these inputs as well as inputs
- )
from other processes, the general manager-Vogtle nuclear operatons is responsible for making sure that proper corrective action is being taken.
~
Reports of significant conditions adverse to quality are
, ;g reviewed by the plant review board, and'its recommendations yy regarding corrective action are forwarded to appropriate 17.2.16-1 Amend. 8 7/84
. VEGP-FSAR-17.
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management personnel.
Verification.'of proper implementation of corrective action program requirements is achieved by the l
quality assurance audit program, as described:in subsection lg-17.2.18.
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0394V 17.2.16-2 Amend. 8 7/84
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VEGP-FSAR-17
'.h 17.2.17 QUALITY ASSURANCE RECORDS Plant procedures require the proper identification of documents
<}
which furnish objective evidence of activities affecting the Z/
quality of the VEGP.
Written procedures which are consistent with applicable codes, standards,'and procurement documents will control the storage and retention of records.
The minimum records to be controlled and retained are described in Technical Specifications section 6.10, Record Retention;
.,}
additional records are retained in accordance with approved procedures.
Typical records include plant history, operating logs, reportable occurrences, results of reviews, inspections, tests, audits, material analyses, qualification of personnel, procedures, and equipment; and other documentation such es drawings, specificatie's, procurement documents, calibration procedures and reports, nonconformance reports, and corrective action reportg.
The superintendent of administration is responsible for the receipt, storage, retrievability, issue, and control of specified plant docum.ents.
Personnel and organizations submitting records and documents to the documentation staff for storage shall be responsible for providing adequate information
-j with that record or document to allow its systematic storage and retrieval.
Inspection records submitted to the documentation staff for storage will be reviewed by the responsible organicatibn to ensure that-the requirements in subsection 17.2.10 are included.
Record storage facilities have been constructed, located, and secured to prevent destruction of applicable records by fire, i
flooding, theft, and deterioration by environmental conditions.
Activities associated with quality assurance records are consistent with the cosition of Regulatory Guide 1.88, Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records, and Regulatory Guide 1.33, Quality
,g Assurance Program Requirements.(Operation), as described in l 4; section 1.9.
1 The quality assurance department will audit _ activities to ensure the records and retention requirements described'herein are implemented.
(See subsection 17.2.18.)
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I 0395V 17.2.17-1
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VEGP-FSAR-17 17.2.18 AUDITS The quality assurance department is responsible for the program
?)
of planned and scheduled audits devised to verify the -
M effectiveness of and compliance withLall aspects of the operatione quality assurance program (OQAP).
The objectives of the qualicy assurance audit system are.to:
A.
Determine that the OQAP has been developed in
,]
accordance with applicable requirements.
B.
Verify by audit that the OQAP has been implemented.
C.
Assess the effectiveness of the OQAP.
D.
Identify program deficiencies.
E.
Verify resolution of deficiencies and nonconformances.
F.
Ensure compliance'with Final Safety Analysis Report 8
commitments.
The quality assurance audit program requirements are! consistent
)
with the provisions of Regulatory Guide 1.33, Quali.ty Assurance Program Requirements (Operation); Regulatory Guide 1.144, Auditing of Quality Assurance Programs:for Nuclear Power Plants; and Regulatory Guide 1.146', Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants, as described in section 1.9.
To satisfy the requirements for the audit system, the following measures :shallEbe established and implemented:
A.
The performance of audits is iniaccordance with written procedures or checklists'and is conducted by.
appropriately trained and qualified personnel not having direct _ responsibilities in the areas being audited.
B.
Audit results are documented, includAng the formal identif* cation of_ problems found and the recommended corrective actions where appropriate, and-are issued through preparation of audit finding reports.
8
([)
C.
Responsible management takes the necessary action _to correct the deficiencie: revealed by the audit.
D.
Deficient areas are monitored until: corrections have l
been accomplished, h )f E.
Audits include an objective' evaluation of quality-related practices, procedures, a'nd instructions; the 17.2.18-1 Amend. 8 7/84
s VEGP-FSAR-17 effectiveness of implementation; and the conformance-F with policy directives.
F.
The audits include the evaluation of work areas, activities, and processes and the review of-vi documents and-records.
G.
The following types of audits shall be performed:
1.
Audits to. provide a comprehensive independent f
verification and evaluation of quality-relate'd procedures and activities to ensure 1that they are-adequate and effectively' comply, with the OQAP requirements.
These-audita are performed under the direction of the Vogtle quality assurance manager.
2.
External audits performed by the Vogtle. quality-assurance manager and principal contractors.on-their suppliers performing-activities on safety-related structures, systems,. andLcomponents.
These audits include verification and evaluation mf their quality assurance program, procedures, and activities to ensure thatethey are adequate-and effectively comply with allvaspect's of the:
OQAP and procedure roquirements.
H.
Audits are regu'larly scheduled onLthe basis.of stat'us-and safety importance of the' activities'being performed; they are initiated early.enough to ensure effective, quality.
Audit schedule: changes, reflecting more frequent audits are required by one orfmore of the following conditions:
1.
When.significant changes are madeTin functional areas of the OQAP, such as significant reorganization or. procedure' revisions.
Vf:
2.
When there is evidence that the performance or.
reliability of safety-related items is in. jeopardy due to deficiencies or nonconformances in the OQAP.
3.
When a systematic, independent assessment 1of OQAP d['
effectiveness is necessary.
4.
When it is necessary'to verify-implementation of required correctivecactions, such as:
L a.
Procedures' control and review.
("
l 17.2.18-2 Amend. 84 7/84-
T VEGP-FSAR-17 2) j 17.2.18 AUDITS The quality assurance department is responsible for.the program
[
"i. }
of planned and scheduled audits devised to verify the effectiveness of and compliance with all aspects of the-operations quality assurance program (OQAP).
The objectives of the quality assurance audit. system are to A.
Determine that the OQAP has been developed in f
. y,..)
accordance with applicable requirements.
B.
. Verify by audit'that the OQAP has been implemented, i
t C.
Assess the effectiveness of the OQAP.
D.
Identify program deficiencies.
E.
Verify resolution of deficiencies and~nonconformances.
F.
Ensure compliance with Final-Safety Analysis Report l8 commitments.
5 The quality assurance audit program requirements are consistent-s
)
with the provisions of Regulatory Guide 1.33, Quali.ty Assurance Program Requirements (Operation);' Regulatory Guide.1.144, Auditing of Quality Assurance Programs for Nuclear Power Plants; and Regulatory Guide 1.146, Qualification of Quality-Assurance Program Audit Personnel for-Nuclear Power Plants, as described in section 1.9.
To satisfy!the requirements for'the audit system, the-following measures shall be established and implemented:
A.
The performance of audits is in accordance with written procedures or checklists and is conducted by=
appropriately trained and qualified personnel not having direct responsibilities in the areas being audited.
B.
Audit results are documented,, including the formal-identification-of. problems found'and the recommended corrective actions where appropriate, and are issued through preparation of audit finding reports.
8'
..(j)
C.
Responsible-management takes-the necessary action to correct the deficiencies revealed by the audit.-
D.
Deficient areas are monitored until corrections have been accomplished.
()
E.
Audits include.an objective evaluation of quality-l related practices, procedures, a'nd instructions; the 17.2.18-1 Amend. 8 7/84
VEC'-FSAR-17 b.
Records management and document control.
c.
.)
d.
Corrective action programs.
The quality assurance audit department will receive formal and on-the-job training prior to the initiation of the OQAP as outlined in this chapter.
The quality
)
assurance department under,the general manager-quality assurance will implement the quality assurance audit system.
Paragraph-17.2.1.3 describes the quality assurance department organization.
Plant management is responsible for making available plant records, reports, log books,'and other quality assurance documents requested by the audit team.
I.
Analysis of audits performed and reports which indicate quality trends and the effectiveness of the OQAP will be provided to management.
During the operating life of the plant, the onsite activities S;
to be audited will include but not be limited to the.following:
A.
Administrative controls and reporting requirements.
B.
Health physics and radiation protection.
C.
Environmental monitoring plant chemistry and environmental technical specification.
D.
Plant chemistry.
E.
Radioactive warte control.
F.
Reactor and plant operations.
W.
O.
Material control (procurement, storage, and issue).
H.
Quality control (nondestructive examination, inspection, training, qualification / certification of g
quality control personnel, etc).
n t@e, v"
I.
Surveillance program.
J.
Test equipment calibration and control.
K.
Balance of plant instrument calibration.
f.
...)
L.
Computer codes.
17.2.18-3 Amend. 8 7/84
{.
f VEOP-FSAR-17
__.a
- 1 M.
Security Plan-and procedures.
N.
Emergency Plan and procedures.
0.
Design changes 7.nd plant modification control;.
kj '
P.
Departmental training programs.-
Q.
Maintenance programs.
goe s R.
Fuel handling and special nuclear material = control 4 S.
Inservi'ce-inspection program.
1
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0396V 17.2.18-4.:
' Amend.L8 ;7/84
1 VEGP-FSAR-17 J
17.2.16 CORRECTIVE ACTION Approved plant procedures shall be written to ensure that conditions adverse to quality, failures, malfunctions,
()
deficiencies, deviations, defective materials and equipment, and nonconformances on safety-related systems are promptly identified, documented, and corrected.
The program described herein requires the identification and corrective action of conditions adverse to quality.
These requirements are consistent with the provisions of Regulatory Guide 1.33,
.s a. ')
Quality Assurance Program Requirements (Operation),
as described in section 1.9.
Provisions for corrective action require that:
A.
Evaluation of conditions adverse to quality and determination of the need for corrective action are in accordance with established approved procedures.
B.
Measures are established to determine the cause of the condition and to institute corrective action to preclude the recurrence of these significant conditions adverse to quality.
)
C.
Measures are established to follow up on co'rrective actions to ensure proper implementation and to close out the corrective action documentation.
D.
Measures are established to document and report to appropriate levels of management significant conditions adverse to qualitys cause of the conditions, and corrective action taken.
Reports of significant conditions adverse to quality are reviewed by the plant review board, and its recommendations-regarding corrective action are forwarded to appropriate management per annel.
Verification of proper implementation of (4.
corrective action is conducted by the quality assurance audit personnel, as described in subsection 17.2.18.
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PAGE 380 U.S.H.R.C.. MANPOWER SYSTEM REGULAR MAN HOURS EXPENDED FOR THE SELECTED DOCKET g\\
09/21/84 FROM CP ISSUE DATE THROUGH END FY '83 REGIDH II - OL REVIEW 05c00424
.V0GTLE 1 REGULAR EMPLOYEE HOURS-
=
HAME
'75 FOR FISCAL YEAR OUT OF OFC SFTY 'INSP. EFFORT COH-SITE) 1TW 3.0 BR0kHLEE,VIRfiIL ~ L 40.0 EM?HME TOTAL DAHIELSON,. DdANE H 12.0 EMPHME TOTAL-WRIGHT, ROBERT.W
'55.0 EMPNME TOTAL ACT-CDDE TOTAL ALL OTHER SFTY INSP EFFORTCPREP-DOC-ENF) 1TO 5.5 BROWHLEE, VIRGIL L 82.0 EMPNME TOTAL DANIELSON, DUAHE H 19.5 EMPNME TOTAL WRIGHT, ROBERT W 107.9 EMPNME TOTAL ACT-CODE TOT AL -
DUT'0F OFC ENVIR INSP EFFCRT (DN-SITE) 2TW 23.0 CUNHINGHAM, ANDREW L 23.0 EMPNME TOTAL ACT-CODE TOTAL IN OFFICE ENVIR INSPECTION EFFORT 2TX 6.0 CUHNINGHAM, ANDREW L 6.0 EMPHME' TOTAL ACT-CODE TOTAL ALL OTHER ENVIR INSPECTIDN EFFORT 2TO 32.0 CUNHINGHAM, ANDREW L 32.0 EMPNME TOTAL 223.0 ACT-CODE TOTAL l
YR TOTAL t
FOR FISCAL YEAR '76 C00 TRAVEL
~
4.0
~l CUNHINGHAM, ANDREW L 4.5
)
EMPHME-10TAL RAUSCH, JOHN K 8.5 EMPHME TOTAL
/
ACT-CODE TOTAL l
1
U.S.H.R.C. MANPOWER SYSTEM PAGE 3$
09/21/34 REGULAR MAN HOURS EXPENDED FOR TME SELECTED DOCKET FROM CP ISSUE DATE THROUGH END FY '83 I
REGION II - OL REVIEW l
05000424 V0GTLE I
_-------------------------y NAME HOURS
_.=
1TW OUT OF OFC SFTY INSP EFFORT-(OH-SITE)
EMPNME TOTAL RAUSCH, JOHN K '
8.0 a.0 ACT-CODE TOTAL 1TX IN OFFICE SAFETY INSPECTION EFFORT EMPNME TOTAL RAUSCH, J0liN K 27.0' 27.0 ACT-CODE TOTAL 1TO ALL OTHER SFTY INSP EFFORTCPREP-DOC-ENF)
EMPHME TOTAL RAUSCH, JOHN K 8.0 8.0 ACT-CODE TOTAL 2TW OUT OF OFC ENVIR INSP EFFORT COH-SITE)
EMPNME TOTAL CUNNINGHAM, ANDREW L 4.0 4.0 ACT-CODE TOTAL I!X IN OFFICE ENVIR INSPECTIDH EFFORT
- EMPNME TOTAL CUNNINGHAM, ANDREW L 8.0 3.0 ACT-CODE TOTAL 63.5 YR TOTAL 7
FOR FISCAL YEAR '77 C00 TRAVEL EMPHME TOTAL B"RYANT, JACK C 1.0 EMPNME TOTAL RAUSCH, JOHN K 14.5
" EMPNME TOTAL WRIGHT, ROBERT W 2.0 17.5 ACT-CODE TOTAL 3
n -
l
' ' ' ~
PAGE 3%
U.S.N.R.C. MANPOWER SYSTEM 09/21/C4 REG'JLAR MAN H;UT.S EXPENDED FOR THE SELECT.D DOCKET FROM CP ISSUE DATE THROUGH END FY 'v,3 REGION II - OL REVIEW 05000424 V0GTLE t RkGULAR EMPLOYEE NAME HOURS n__
1TW OUT OF OFC SFTY INSP EFFORT (OH-SITE) 85.0 EMPNME TOTAL BRYANT, JACK C 33.0 EMPNME TOTAL RAUSCH, JOHN K 6.0 EMPNME TOTAL WRIGHT, ROBERT W 54.0 ACT-CODE TOTAL 1TX IN OFFICE SAFETY INSPECTION EFFORT 14.0 EMPNME TOTAL RAUSCH, JOHN K 14.0 ACT-CODE TOTAL 1TO ALL OTHER SFTY INSP EFFORT (PREP-DCC-EHF) 60.0 EMPNME TOTAL RAUSCH, JOHN K 2.0 EMPNME TOTAL SWAN,WALLACE B 7.0 EMPNME TOTAL WRIGHT, ROBERT W 69.0 ACT-CODE TOTAL 2TO ALL OTHER ENVIR INSPECTION EFFORT 9.0 CUNNINGHAM, ANDREW L EMPNME TOTAL 9.0 ACT-CODE TOTAL 163.5
-- YK TOTAL FOR FISCAL YEAR '78 CCO TRAVEL 4.0 EMPNME TOTAL COMPTON, ROBERT M 2.0 EMPNME TOTAL CIBBONS, THOMAS D 2.0 HUNT, MILTON D EMPNME TOTAL 4.0 LENAHAN, JOE EMPNME TOTAL 4.0 RAUSCH, JOHN K
' EMPNME TOTAL 6.0 SWAN,WALLACE B EMPNME TOTAL 22.0 ACT-CODE TOTAL
'M I
PAGE 38-U.S.H.R.C. MANPOWER SYSTEM REGULAR MAN HOURS EXPENDED FOR THE SELECTED DOCKET 09/21/84 FROM CP ISSUE DATE THROUGH END FY '83 '
REGION II - OL REVIEW 05000424 V0GTLE 1
---e REGULAR EMPLOYEE HOURS HAME 1TW OUT OF OFC SFTY INSP EFFORT (OH-SITE) 12.0 COMPTON, ROBERT M 14.0 EMPNME TOTAL GIBBONS, THOMAS D 6.5 EMPNME TOTAL HUNT, MILT 0H D 12.0 EMPNME TOTAL-LENAHAN, JOE 38.5 EMPNME TOTAL RAUSCH, JOHN K
~31.0 EMPNME TOTAL SWAN,WALLACE B 114.0 EMPNME TOTAL ACT-CODE TOTAL' 1TX IN OFFICE SAFETY INSPECTIDH EFFORT 2.0 RAUSCH, JOHN K 4.0 EMPHME TOTAL SWAN,WALLACE B 6.0 EMPNME TOTAL
' ACT-CODE TOTAL l
1 ALL OTHER SFTY INSP EFf0RT(PREP-DOC-EHF) l.*
1TO i
14.0 l
COMPTON, ROBERT M 19.0 EMPNME TOTAL GIBBONS, THOMAS D 28.0
)
EMPNME TOTAL LEHAHAH, JOE 45.5 EMPNME TOTAL RAUSCH, JOHN K 28.0 EMPHME TOTAL SWAN,WALLACE B 134.5 EMPNME TOTAL 276.5 ACT-CODE TOTAL YR TOTAL FOR FISCAL YEAR '79 C00 TRAVEL 4.0 ANG WILLIAM P 7.0 EMPNME TOTAL HARRIS, JOHN R 4.0 EMPNME TOTAL HERDT, ALAN R 23.0 EMPNME TOTAL HUNT, MILT 0H D
.0 EMPNME TOTAL MODEHOS, LEO 4.0
~~EMPNME TOTAL SWAN,WALLACE B 42.0 EMPNME TOTAL ACT-CODE TOTAL M
e
.~
PAGE'39C 19?/21/04
~
U.S.N.R.C.-MANPOWER SYSTEM -
' REGULAR MAN HEURS' EXPENDED FCR THE SELECTED DOCKET FROM CP ISSUE DATE.THROUGH END FY tS3'
-REGION II.'- OL; REVIEW-05000424- ~'V0GTLE 1-
-EMPLOYEE.
REGULAR
^
- DO C ' ROUTINELDOCUMENTATION.
'GOU'GE, MICH A EL.) '-
- 12. 0 --
2EMPMME.
TOTAL
.48.0 EMPNME m TOTAL-HARRIS, JOHN R-
.163.5.
' EMPNME '. ? TOTAL
' HUNT,. MILTON D.
EMPNME: ~TOTAti LENAHAN, JOE.
38.0 l EMPNME.'- TOTAL-
'.MODEN05,. LED
- 30.0 5. 0 '-
TEMPNME aTOTALL SWAN,WALLACE B
.296.5
- ACT-CODE: TOTAL
'J 0M i ADMINISTRATIVE. SUPPORT' '
'EMPNME,, TOTAL" HUNT, MILTON D-77.0.
77.0
. ACT-CODE TOTAL -
PAP-ROUTIME' PREPARATION EMPMME- -TOTAL-
.CUNNINGHAM, ANDREW L 15.0 1.0'
,EMPNME TOTAL GOUGE, MICHAEL J.
'EMPNME TOTAL HARRIS, JOHN R.
143.0
- EMPNME TOTAL HUNT, MILTON D -
21.0-EMPMME TOTAL LENAHAN, JOE 29.0-30.0 lEMPNME. TOTAL
- MODENDS, LED 239.0
- ACT-CODE TOTit 3'..'
PP1 R
NE INSPECTION GOUGE,' MICHAEL J 2f.8 EMPMME TOTAL 62.0 rs EMPNME.
. TOTAL '
' HARRIS, JOHN R 28.0' L-EMPNME ~ TOTAL HERDT, ALAN R.
"103.0 i EMPNME.. TOTAL HUNT, MILTON D EMPNME : TOTAL-LENAHAN, JOE 40.0 EMPNME TOTAL MODENOS, LED 48.0
.EMPNME TOTAL VALLISH, EDWARD J-1.0 303.0
?ACT-CODE TOTAL
--__._-_L.
T'.t PAGE:391 U.S.N.R.C. MANPOWER. SYSTEM 189/21/84'
- REGULAR MAN H@UCS EXPENDED;FOR THE SELECTED. DOCKET.
FROM.CP ISSUE.DATE THROUGH END FY.: 83
. REGION IIL.- OL' REVIEW
'85008424 lV0GTLE: 1.
a_.
REGULAR ~
' EMPLOYEE
, HOURS-
-NAME PR1-REACTIVE ONSITE/0FFISTE'INSPECTIDN' HARRIS,' JOHN R.
2.9
'LENAHANh JOE:
. g _,0,:
4.
- EMPNME.. TDTALL
.EMPNME)^iTOTALL i ACT-C0DEJTDTAL.-
.-e HUNT, MILTON D
^
' 10 '. 9.
10.9
EMPNME' TOTAL-
- ACT-CODE. TOTAL :
,1TW
.0UT'OF'0FC SFTY INSP. EFFORT (ON-SITE).'
8.8-ANG.. WILLIAM P.
.8.8-
' EMPNME::
TOTAL SWAN,WALLACE 5 16.8;
'EMPNME
.L. TOTAL 1
. ACT-CODE TOTAL 1T O ALL OTHER SFTY,.INSP EFFORTCPREP-DOC-ENF) 5.0-
'LANG, WILLIAM P
. HUNT, MILTON D
~
5.0
-EMPNME ETOTAL-6.8
'RAUSch,~ JOHN K' 6.0:
'EMPNME.
' TOTAL, SWAN,WALLACE.B' Er1PNME.: TOTAL-
.. 22.0
- ACT-CODE TOTAL..
1,011.5'
' nYR:
TOTAL POR. FISCAL YEAR '88-CSS TRAVEL.
1.5-BROWNLEE, VIRGIL
.2.0 EMPNME TOTAL'-
.CANTRELL, FLOYD..
6.5-
' EMPNrtE' TOTAL.
CROWLEY, BILLY R-
.0'
- EMPNFIE '
TOTAL.
HARRIS, JOHN R EMPMME
- J TOTAL 10.8
.ACT-CODE TOTAL
-g.
- .i.- -
t 1
_m..--
397J L89/28/04' U.S.H.R.C. MANPOWER SYSTEM
~PAGE~5 T,..
REGULAR MAN HOURS EXPENDED FOR..THE. SELECTED.. DOCKET:
FROM CP ISSUE DATE..THROUGH END FY' '83 L-REGION-II - OL' REVIEW
,.3 e'L
~05000424 V0GTLE 1-
~
4
~ EMPLOYEE REGULAR:
NAME.
HOURS D S C-ROUTINE DOCUMENTATION EMPMME... TOTAL.
BROWHLEE, VIRGIL 12.00 EMPNME : TOTAL.-
CROWLEY, BILLY.R~...
< 2 9. 0 1.
- EMPKME.. TOT AL L CUNNINGHAM,..ANDREM L-.
- 21. 0
EMPNME l TOTAL.
..GERARD, EDWARD H-10.0
'EMPNME TOTAL-HARRIS,-JOHN R 28.0.
EMPNME-TOTAL HUNT, MILTON D'
'16340.
EMPMME~
TOTAL LENAHAN,. JOE'.
. 9. 0.
.. EMPMME :TOTALn MCFARLAND.'C R1,.
12.0
.. EMPNME -
TOTAL
-THOMAS,.MCKENZIE'
. 16.0:
- EMPNME- : TOTAL ~
VAND00RN,. PETER K 8.0 EMPNME.
TOTAL' l WRIGHT, ROBERT 2.0-
'310.0
.. ACT-CODE' TOTAL-J8M ADMINISTRATIVE SUPPORT-
.EMPMME- ' TOTAL HUNT, MILTON D 99.0 99.0 ACT-CODE TOTAL.
PAP ROUTINE PREPARATION
'EMPNME ~. TOTAL
.BROWHLEE,: VIRGIL 1.5-EMPNME
- TOTAL CROWLEY, BILLY R-2.8 e
EMPNME TOTAL GERARD, EDWARD H 3.0-
'EMPMME
. TOTAL-HARRIS, JOHN R 12.0-1EMPNME TOTAL LENANAN,. JOE
~
16.0 EMPNME
- iOTAL HUNT, MILTON D 3.0 4
- EMPNME' TOTAL-MCFARLAND, C R.
4.0 EMPNME-. TOTAL THOMAS McKENZIE 8.0 EMPNME; TOTAL WRIGHT, ROBERT 1.0.
50.5 ACT-CODE. TOTAL
' ppt ROUTINE INSPECTION EMPNME
. TOTf.L BROWHLEE,' VIRGIL 7.5 EMPNME TOTAL CROWLEY, BILLY R 25.5 EMPNME TOTAL CUNNINGHAM, ANDREW L 12.0 l M '
09/21/GS U.S.H.R.C.' MANPOWER SYSTEM REGULAR MAN HOURS EXPENDED FOR THE SELECTED DOCKET
'PAGE 3E FROM CP ISSUE DATE THROUGH END FY '83 REGION II - OL REVIEW 05000424 V0GTLE 1
- - ~ ~ ~
EMPLOYEE REGULAR
________3 HAME I
HOURS PP1 ROUTINE INSPECTION
'EMPNME TOTAL EMPNME TOTAL GERARD, EDWARD H.
EMPNME TOTAL HARRIS. JOHN R 13.0 EMPNME TOTAL HUNT, MILTON D.
36.0-EMPWME YOTAL LENAHAN, JOE 71.5 8.0
-EMPNME TOTAL MCFARLAND, CR EMPNME TOTAL THOMAS, MCKENZIE 11.0 i
22.0 ACT-CODE TOTAL VAND00RN, PETER K 16.0 222.5 PRt REACTIVE ONSITE/0FFIS'E INSPECTION ENPNME TOTAL EMPNME TOTAL CANTRELL, FLOYD EMPNME TOTAL HARRIS, JOHN R 4.0 EMPNME TOTAL HUNT, MILTON D 173.0 28.0 EMPNME TOTAL LENAHAN, JOE ACT-CODE TOTAL WRIGHT, ROBERT 55.0 1.0 261.0 RT1 INCIDENT / ACCIDENT RESPONSE EMPNME TOTAL ACT-CODE TOTAL MURPHY, CHARLES E 12.0
- YR TOTAL 12.0 965.0 FOR FISCAL YEAR '81 BR1 REACTIVE PREPARATION EMPNME TOTAL EMPNME TOTAL HOWELL, JERRY C EMPNME TOTAL LENAHAN, JOE 3.0
_,ACT-CODE TOTAL WRIGHT, R 6.0 2.0 11.0 C01 DOCKET TRAVEL EMPNME TOTAL EMPNME TOTAL CROWLEY, BILLY R DEBBAGE, ARTHUR G.
3.0 2.5 1
_ _ _. _ _, _, _ _ -. = -. _ _.
U.S.N.R.C. MANP0WER SYSTEM PAGE'39 L O9/21/24
- EEGULAR MAN' HOURS: EXPENDED FOR THE SELECTED-DOCKET FROM CP. ISSUE DATE 'THROUGH : END - FY '83 :
REGION I'I - OL REVIEW 85000424 V0GTLE.1-
' EMPLOYEE:
REGUL AR.-
HAME-
- HOURS C81
- : DOCKET TRAVEL
.GIRARD,' EDWARD'H 4.0'
~
EMPNME- : TOTAL.
.3.0; EMPNME-TOTAL.
HARRIS, JOHN R.
EMPNME" ' TOTAL _
HOWELL,, JERRY C'..
12.0.
EMPNME -- TOTAL KLEINS0RGE, WILLIAM P-6.0' i
EMPNME TOTAL
'LENAHAM, JOE.
.14.0 I
.EMPMME1 TOTAL VGRSE, JAMES-Y:
40.0
, 2. 5 EMPNME' TOTAL
- WRIGHT, R-"
87;0 ACT-CODE TOTAL DR1-7 REACTIVE DOCUMENTATION.
EMPNME' TOTAL.
AL DERSON, CARL". E.--
2.0
' EMPNME :
2 TOTAL GIRARD, EDWARD H.
6.0-8.0 ENPNME
,.T O T A L
. HARRIS,- JOHN R :
4.0' H : EMPNME:-
T O T A L :-
HOWELL", JERRY Ca
. 73.0' JEMPNMEL LTOTAL'
-LENAHAN, JOE-1.0 EMPNME-TOTAL VAND00RN, PETER K
.EMPNME.
TOTAL VORSE, JAMES Y..
57.0, 151.0 VACT-CODE TOTAL DOC ROUTINE DOCUMENTATION-20.0.
EMPNME' TOTAL CROWLEY. BILLY R-JEMPNME TOTAL GIRARD, EDWARD H 13.2
'38.0 EMPMME :. LTOTAL HARRIS, JOHN R.
- - >EMPNME
. TOTAL HUNT, MILTOK D 8.0
[
'EMPNME- : TOTAL KLEINSORGE, WILLIAM P 20.0' EMPNME TOTAL-WRIGHT, R 15.0.
114.2 1ACT-CODE TOTAL-PAP ROUTINE PREPARATION
.EMPNME TOTAL GIRARD, EDWARD H 5.0 HARRIS, JOHN R 21.0 EMPNME TOTAL 4.0 HUNT,. MILTON D
'EMPNME TOTAL KLEINSORGE, WILLIAM P 10.0 EMPNME-TOTAL M
j i89/21/C4 U.S.N.R.C. MANP WER SYSTEM-PAGE 395
- REGULAR MAI; HOURS : EXPENDED FOR-THE SELECTED DOCKETL -
i FROM CP. ISSUE DATE :THROUGH END FY '83 REGION'II - OL' REVIEW:
05000424 V0GTLE 1-
" EMPLOYEE REGULAR HAMEJ cHOURS PAP
' ROUTIN E' PREPARATION VORSE, JAMES Y-4.0 EMPNME.. TOTAL
. WRIGHT, R 12.0:
EMPNME... TOTAL
'56.0
'ACT-CODE TOTAL' PP1 ROUTINE-INSPECTIDH' EMPNME -TOTAL CROWLEY, BILLY R
~
~14.0
.EMPNME ' TOTAL
- DEBBAGE, ARTHUR.G...
' 17. 0 '
EMPNME TOTAL-ECONOMOS,-MICK 1.0 EMPNME
' TOTAL-
- GIR ARD,' EDWARD H.
12.6 EMPNME TOTAL-HARRIS, JOHN R' 41.0'
.EMPhME.
TOTAL KLEINSORGE, WILLIAM P-.
-26.0 EMPNME. TOTAL WRIGHT, R
~17,0; ACT-CODE TOTAL 128.61 PRI REACTIVE ONSITE/0FFISTE INSPECTION EMPNME TOTAL ECONOMOS, NICK 4.0
'EMPMME
. TOTAL GIBBONS,. THOMAS D 1.5 EMPNME TOTAL GIRARD, EDWARD H-3.0 EMPNME-TOTAL WRIGHT, R 4.0-12.5 LACT-CODE: TOTAL P1V INVESTIGATION EMPNME-TOTAL ALDERSON, CARL E 2.5 EMPMME TOTAL HOWELL, JERRY C 25.0 EMPNME TOTAL LENAHAN, JOE 47.0.
EMPNME TOTAL VORSE, JAMES Y' 92.5 167.0
_ACT-CODE TOTAL
-SR1
-SITE PUBLIC RELATIONS-EMPNME TOTAL HARRIS, JOHN R 4.8' 4.0 ACT-CODE TOTAL
PAGE 396-U.S.N.R.C. MANPUWE'R SYSTEM
~
REGULAR MAN HOURS EXPENDED FOR THE SELECTED DOCKET 09/21/84 FROM CP. ISSUE DATE THROUGH END FY '83 REGION II - OL REVTEW 05000424 V0GTLE: 1
-.......................q REGULAR
' EMPLOYEE
. HOURS HAME
. SR 1 SITE PUBLIC RELATIONS
~731.3,
'YR-
- . TOTAL a
' FOR FISCAL -YEAR '82 BR1 REACTIVE PREPARATION 4.0 i
HARRIS, JOHN R.
5.0 EMPNME
' TOTAL HUNT, MILTON D 8.0 EMPNME TOTAL SWAN,'WALLACE-B 20.0' EMPNME TOTAL ~
TOBIN, WILLIAM:J 37.0 EMPNME TOTAL ACT-CODE TOTAL C01-DOCKET TRAVEL 4.0 COLEY, JAMES'L JR.
5.0:
EMPNME TOTAL DEBBAGE, ARTHUR G.
5.5 EMPHME TOTAL GIRARD, EDWARD H 15.0 EMPNME'. TOTAL HARRIS, JOHN R 3.0 EMPNME TOTAL HOLMES-RAY, PETER 4.0 EMPNME TOTAL HUNT, MILTON D 10.0 EMPNME TOTAL KLEINSORGE, WILLIAM P-3.0 EMPNME.
TOTAL LENAHAN, JOE
5.0 EMPNME
TOTAL.
LIU, WAN-CHENG 4.5
. EMPMME TOTAL MCFARLAND, C R 3.5 EMPNME TOTAL MERRIWEATHER,'HORMAN 9.0
~ -EMPNME TOTAL
.. RUFF, ALBERT.B 16.0 EMPNME TOTAL-SANDERS, WILLIAM F
.0
~ 'EMPNME TOTAL SWAN, WALLACE 5:
17.0 EMPNME TOTAL
'TOBIH, WILLIAM J 7.5-EMPNME TOTAL WRIGHT, R 112.0 EMPNME TOTAL ACT-CODE TOTAL DR1 REACTIVE DOCUMENTATION 5.0 ALDERSON, CARL E 2.0 EMPNME TOTAL CONER CHARLES E 3.0 EMPNME TOTAL HOWELL, JERRY C 7.0 EMPMME TOTAL HUNT, MILTON D-EMPNME TOTAL 6
___ _ _.= _ _ _
PAGE.39 U.S.N.R.C.JMANPOWER. SYSTEM'
' 09/21/G4 CEGULAR MAN HOURS EXPENDED'FOR THE SELECTED DOCKET
.FROM CP ISSUE DATE THROUGH..END..FY '83 REGION.II~- OL' REVIEW-05000424-V0GTLE:t
.' EMPLOYEE.
. REGULAR' NAME.
. HOURS,.
DR1
-REACTIVE:DOCUMENTATIbH-
-EMPNME'. TOTAL
- LENAHAN,' JOE;
~
6.0,
-1.0
' EMPNMEL:- TOTAL
.ROGGE. JOHN 54.0:
EMPNME TOTAL TOBIN,.'JILLI AM J.
3.0-
- EMPNME.
'OTAL-
~V0rtSE, JAMES Y.
.5.0-EMPNME.. TOTAL'
'WILLIAMSON, EVERETTL 86.0 c ACT-CODE-TOTAL DOC ROUTINE. DOCUMENTATION -
.EMPNME-TOTAL COLEY,IJAMES L:JR-21.0 EMPNME:
TOTAL-DEBBAGE,' ARTHUR G.-
79.0-
'EMPNME' ' TOTAL-GIRARD,' EDWARD H-
- 25.0-46.0
- 1. EMPNME TOTAL HARRIS, JOHN R
.8.0 EMPNME TOTAL:
HUNT ' MILTON'D EMPNME TOTAL-
.KLEINS0RGE, WILLIAM P 43.0" 14.0 EMPNME-TOTAL' LENAHAN,' JOE EMPNME:. TOTAL MCFARLAND, C R=
14.0' EMPNME
' TOTAL
'MERRIWEATHER,'HORMAN 41.0, 32.0 cEMPNME TOTAL ROGGE, JOHN -
EMPNME-TOTAL RUFF, ALBERT B 5.0-EMPNME
- TOTAL-St.NDERS, WILLI AM F -
31.0 i
'4.0 EMPNME
' TOTAL-SWAN, WALLACE'B 57.G-EMPNME.-TOTAL-WRIGHT, R
.470.0 l
ACT-CODE TOTAL:-
q
)
PAP ROUTIME PREPARATION
+
1.0L EMPNME
' TOTAL ~
DEBBAGE, ARTHUR G.'
5.8-EMPNME-TOTAL.
G!?ARD, EDWARD H EMPNME TOTAL MAG RIS, JOHN R -
25.0 l
-HGlMES-RAY, PETER 3.0-EMPNME-TOTAL KLEINSORGE, WILLIAM.P 23.0
'" EMPNME l TOTAL 4.0 EMPNME TOTAL LIU, WAN-CHENG-MCFARLAND, C R 4.0:
EMPNME-TOTAL
-MERRIWEATHER,' NORMAN 21.0 EMPNME-TOTAL:
RUFF, ALBERT B' 26.0
' EMPNME TOTAL SANDERS, WILLIAM F'
'106.0 EMPNME TOTAL
.+-
L __
PAGE 39!2 U.S.N.R.C. MANPOWER SYSTEPs 0 *t/21/fJ4 REGULAR MAN HOURS EXPENDED FOR THE SELECTED DOCKET
..FROM CP ISSUE DATE THROUGH END FY '33 '
REGION II - OL REVIEW 05000424 V0GTLE 1
-e EMPLOYEE REGULAR NAME '
HOUEs.
PAP ROUTINE PREPARATION -
19.0 EMPNME TOTAL WRIGHT, R
.234.0 ACT-CODE TOTAL PE1 ENFORCEMENT EMPNME-TOTAL HUNT, MILTON D 0
.0 ACT-CODE TOFAL PP1 ROUTINE INSPECTION EMPNME TOTAL COLEY, JAMES L JR 30.0 27.0 EMPNME TOTAL DEBBAGE, ARTHUR G.
18.0 EMPNME TOTAL.
GIRARD, EDWARD H 62.0 EMPNME TOTAL HARRIS, JOHN R EMPNME TOTAL HOLMES-RAY, PETER 10.0 EMPNME-TOTAL
-KLEIN50RGE, WILLIAM P 54.0 8.0 EMPNME TOTAL LENAHAN, JOE 15.0 EMPNME TOTAL LIU, WAN-CHENG:
15.5 EMPNME TOTAL MCFARLAND, C R
- EMPNME TCTAL MERRIWEATHER, NORMAN 28.5 14.0 EMPNME TCTAL ROGGE, JOHN 19.0 EMPNME TOTAL RUFF, ALBERT B SANDERS, WILLIAM F 652.0 EMPNME TOTAL 41.5 EMPNME.
TOTAL WRIGHT, R.
994.5
. ACT-CODE TOTAL PR1
. REACTIVE ONSITE/0FFISTE INSPECTION COLEY, JAMES L JR 2.0 EMPNME TOTAL-DEBBAGE. ARTHUR G.
40.0 EMPNME TOTAL GIRARD, EDWARD H 2.0
~EMPNME TOTAL i
HARRIS, JOHN R 50.0 l
EMPNME TOTAL LENAHAN, JOE 16.P EMPNME TOTAL MERRIWEATHER, NORMAN 1.s EMPNME TOTAL 10.?
RUFF, ALBERT B EMPNME-TOTAL 15 WRIGHT,.R EMPNME TOTAL 6
L t.______
-- ~
'PAGE'39%
U.S.H.R.C. MANPOWER SYSTEM
'89/21/84 REGULAR MAN HOURS EXPENDED FOR THE SELECTED. DOCKET
-FROM CP ISSUE DATE:THROUGH END FY'83'-
=REGIDH II - OL' REVIEW
+____&
05000424 V0GTLE 1 LREGULAR-EMPLOYEE:
. HOURS
-5 MAME-1 1
PR1' REACTIVE ONSITE/0FFISTE INSPECTION.
140.0 ACT-CODE - TOT AL'..
P1V
- INVESTIGATION 3 f.0' HARRISE JOHN R 1.0
.EMPNME-TOTAL.
HOWELL, JERRY.C 21.0
'EMPNME. TOTAL-HUNT, MILTON D 2.0' EMPNME TOTAL' ROGGE, JOHN-3.0:
'EMPNME TOTAL RUFF, ALBERT B 49.0.
EMPNME TOTAL TOBIN, WILLIAM J 23.*
EMPNME TOTAL VORSE,' JAMES Y
- 6. G
- - -.EMPNME TOTAL' WILLIAMSON,.EVERETT
.136.5 x EMPNME TOTAL-ACT-CDDE TOTAL SR1 SITE PUBLIC RELATIONS 4.0 SANDERS, WILLIAM F 4.0 "EMPNME TOTAL 2,214.0 ACT-CODE TOTAL -
'YR ~
TOTAL FOR FISCAL YEAR '83NOT RELATED TO'AN ACTIVITY CODE 142.0 L g f'9
- f. '# ^ $. V
~
8 i
JOHNSON, ARTHUR H 44.0 f
D EMPMME-TOTAL
'NORRIS TIMOTHY L.
186.0 p
EMPNME.
TOTAL ACT-CODE TOTAL
.g BR1 REACTIVE PREPARATION
~
8.0 DEBBAGE, ARTiiUR G 1.5 EMPMME TOTAL GIRARD,. EDWARD H 1.0 EMPNME TOTAL HARRIS, JOHN 1t 10.5 EMPNME TOTAL ACT-CDDE ' TOT AL
- - - - - - - - ~ - - _ - _ _ _ _ _ _
m
PAGE 400
'U.S.H.R.C. MANPOWER SYSTEM REGULAR MAh HOURS EXPENDED FOR THE SELECTED DOCKET 89/21/84 FROM CP ISSUE DATE.THROUGH END FY,'83 REGION II - CL REVIEW-05080424-V0GTLE 1
-H
~ _ -.
REGULAR EMPLOYEE.
HOURS NAME-CD1 DOCKET TRAVEL.
4.0 GIBBONS,-THOMAS D 10.0' EMPNME..- TOT AL GIRARD,. EDWARD H
'10.0 EMPNME : TOTAL.
HARRIS, JOHN-R:
.3.0 EMPNME. TOTAL HUNT, MILTON D.
- 3.0
.'EMPNME TOTAL JACKSOH, LOUIE ~H 1.0 EMPNME TOTAL
.KLEINSORGE, WILLIAM P 4.0 EMPNME
. TOTAL-LENAHAN, JOE.
7.0 EMPNME TOTAL-LIU, WAN-CHENG.
- 4.0'
!EMPNME :' TOTAL ROGGE, JOHN F ~
7. 0 -'
.EMPNME TOTAL RUFF, ALSEAT B 17.0 EMPNME TOTAL.
SANDERS, WILLIAM F-
'3.0 EMPNME TOTAL' STETKA, THOMAS F 6.0 EMPNME TOTAL YORK, JOHN W EMPNME TOTAL B4.0 ACT-CODE TOTAL l DR1 REACTIVE DOCUMENTATI0H 4.0 GIRARD, EDWARD H 4.0 EMPNME. TOTAL LENAHAN, JOE 6.O' EMPNME : TOTAL NEJFELT, GREGORY M 1.0 EMPNME TOTAL ROGGE, JOHN F 15,0 EMPNME TOTAL ACT-CODE TOTAL f
DOC ROUTINE DOCUMENTATION 12.0 i
GIBBONS, THOMAS D 34 11 EMPNME TOTAL GIRARD, EDWARD H SS.D EMPNME
. TOTAL HARRIS, JOHN R 48.0
. EMPNME '
TOTAL JACKSON, LOUIE H.
12.0 EMPNME TOTAL KLEIN50RGE, WILLIAM P 22.0 EMPNME TGTAL LENAHAN, JOE 72.0 EMPNME-TOTAL LIU, WAN-CHENF 5.0
~~EMPNME TOTAL MCFARLAND, CHARLES R 6.0 EMPNME TOTAL NEJFELT, GREGORY M 25.0 EMPNME TOTAL ROGGhc -JOHN F-25.0 EMPNME TOTAL' RUFF, ALBERT B 89.0 EMPNME TOTAL SANDERS,*!L1?AM F 4
EMPNME-TOTAL 6
g Y
P*GE C U.S.C.D.C. MANPOWE:2 SYSTEM l
00/21/00 CEGULAR MAN HOURS EXPENDED FOR THE SELECTED DOCKET 1
FROM CP ISSUE DATE THROUGH END FY '83 REGIDH II - OL REVIEM 05080424 V0GTLE t REGULAR EMPLOTEE HOURS NAME DSC ROUTINE DCOUMENTATION 13.0 WRIGHT, ROBERT W EMPNME TOTAL 24.0 YORK, JCHN W l
402.0 EMPNME TOTAL ACT-CDDE TOT AL LEP LICENSING - EMERGENCY PREPAREDNESS 23.5 JACKSON, LOU!E H EMPNME TOTAL 16.0 WRIGHT, ROBERT W EMPNME TOTAL 37.5 CCT-CODE TOTAL PAP ROUTINE PREPARATION 24.0 GIRARD, EDWARD H Ef*.PNME TOTAL 26.0 HARRIS, JOHN R EMPNME TOTAL 10.0 HUNT, MILTON D EMPNME TOTAL 41.0 JACKSON, LOUJE H 8.0
- EMPNME TOTAL KLEINSDRGE, WILLIAM P 4.0 EMPNME TOTAL LENAHAN, JOE 17.0 EMPNME TOTAL LIU, WAN-CHENG 6.0 EMPNME TOTAL MCFARLAND, CHARLES R 4.0
{
EMPNME TOTAL ROGGE, JOHN F EMPNttE TOTAL 16.0 RUFF, ALBERT B 62.0 EMPNME TOTAL SANDERS, WILLIAM F 0
EMPNME
~0TAL STETKA. THOMAS F 6.0 EMPNME
'OTAL WRIGHT, ROBERT W 4.6 EMPNME Y'JI AL YORK, JOHN W EMPNME TOTAL 228.0 ACT-CDDE TOTAL PE1 ENFORCEMENT 2.0 ROGGE, JOHN F
~EMPNME TOTAL 2.0 cCT-CDDE 'OTAL i
.l
4 4 PAGE 40,fd U.S.H.R.C. MANPOWED SYSTEM "e t R 00/21/Q4 REGULAR MAM HOURS EXPENDED F0ct THE SELECTED DOCKET Y
FROM CP ISSUE DATE THROUGH END FY ?83
.. ;P REGION II - OL REVIEW 05000424 VGGTLE 1 REGULAR Em'LOYEE HOURS NAME PP1 RDUTINE INSPECTION 3.0 ANG, WILLIAM P EMPNME TOTAL 12.0 GIBBONS. THOMAS D EMPNME TOTAL 52.5 GIRARD, EDWARD H EMPNME TOTAL 52.0 HARRIS, JOHN R EMPNME TorAL 11.0 HUNT, MILTON D 73.0 EMPNME TOTAL JACKSON, LOUIE H EMPNME TOTAL 15.0 KLEINSORCE. WILLIAM P EMPNME TOTAL 31.0 LENAHAN, JOE EMPNME TOTAL 86.0 LIU, WAN-CHFNG EMPNME TOTAL 24.0 MCFARLAND, (HARLES R EMPNME TOTAL 86.0 ROGGE, JOHN F EMPNME TOTAL 28.0 RUFF, ALBERT B EMPNME TOTAL 698.0 SANDERS, WILLIAM F EMPNME TOTAL 6.0 STEIKA, THOMAS F EMPNME TOTAL 16.0 WRIGHT, ROBERT W EMPNME iOTAL 40.0 YORK, JOHN W EMPNME TOTAL 1,238.5 ACT-CODE TOTAL PR1 REACTIVE ONSITE/0FFISTE INSPECTION 8.0 DEBEAGE, ARTHUR G 8.0 EMPNME TOTAL GIBBONS, THOMAS D EMPMME TOTAL 9.0 GIRARD, EDkARD H EMPNME TOTAL 26.0 HARRIS, JOHN R EMPNME TOTAL 3.0 ROGGE, JOHN F EMPNME TOTAL 1.0 RUFF, ALBERT B 13.0 EMPNME TOTAL SANDERS, WILLIAM F EMPNME TOTAL 2.0 TODD, GREGORY A EMPNME TOTAL 9.5 WRIGHT, ROBERT W EMP9tME TOTAL 79.5 ACT-CODE TOTAL P1V INVESTIGATION 6.0 HARRIS, JOHN R EMPNME TGTAL 2.0 RUFF, ALBERT R 32.0 EMPNME TETAL TODD GREGORY A EMPNME TOTAL 5.0 URTC, BRUMD EMPNME TOTAL
a PAGE 483 U.S.C.C.C. MANPOWER SYSTEM 00/21/83 REGUL AR MAN HOURS EXPENDED FOR THE SELECTED DOCKET FROM OP ISSUE DATE THRCUGH END FY '83 REGION II - GL REVIEW 05000424 V0GTLE 1 EMPLOYEE REGULAR NAME HOURS P1V INVESTIGATION 45.0 ACT-CODE TOTAL QAT QA CHANGE REVIEWS 1 TOPICALS EMPNME TOTAL JACKSON, LOUIE H 8.0 EMPNME TOTAL MRIGHT, ROBERT W 21.0 29.0 ACT-CocE TOTAL 2.357.P Ya TOTAL 3,005.3 CDCKETHD TOTAL 6
e i
n
09/21/84 U.S.N.R.C. MANPOWER SYSTEM PAGE 9 REGtMAR MAN HOURS EXPENDED FOR THE SELECTED DOCKET sv h FOR BLANt ACT-CODES FROM CP ISSUE DATE THROUGH END FY '83 REGION II - OL REVIE'id 05000424 VOGTLE 1 EMPLOYEE REGULAR WAME HOURS FOR FISCAL YEAR *23 1321 PotJIIR FACIL. REPLACEMENT EXAM EMPto!
TOTAL NORRIS. TIMOTHY L 44.0 j PA-WuM TOTAL 44.0 s
i
\\
134 CERTIFICATION EXAMINATIONS r
.i I (pH Emet.ME TOTAL JOHNSON, ARTHUR H 142.0 j
PA-hum TOTAL 142.0 VR TOTAL 186.0 DOCRETNO TOTAL 185.0
- ,,M*
TITLE TOTAL I.248.0
~
t e
I-09/20/24 U.S.N.R.Cc MANPOWER SYSTEM J
'PAGE 31.
REGULAR MAN HOURS EXPENDED FOR THE SELECTED DOCKETS -
L FOR FISCAL YEAR '34 THRU 06/23/84 i
REGION II - OL REVIEW.
C5000424 VOGTLE I
,i i
3 REVIEWER NAME OF REGULAR l
INITIALS REVIEWER HOURS APD ROUTINE DOCUMENTATION
-REV-INIT TOTAL CIL
-WCLIU 24.0 REV-INIT TOTAL
.CSM CRMCFARLA W ;
T.O REV-INIT TOTAL EHG EHGIRARO REV-INIT TOTAL FFS WFSANDERS-.
12.0 7
53.0' REV-INIT TOTAL GMN GMNEJFELT 2.0 -
1 REV-INIT TOTAL HJC JLCOLEY 16.0 i
REV-INIT TOTAL JHO JRHARRIS 47.0
.REV-INIT TOTAL JRR JFROGGE I4.0 i
j~
REV-INIT TOTAL Lt;J LHJACKSON 20.0 ?
REV-INIT TOTAL MNH DOHUNT 24.0 i
REV-INIT TOTAL NGM N MERRIWEATHER 36.0 REV-INIT TOTAL RHR RWWRIGHT 30.0
'i REV-INIT TOTAL WJT WJTOSIN 3.0 ACT-CODE TOTAL 293.0 API ROUTIpeE ON-SITE /OFF-SITE INSPECTION.
REV-INIT TOTAL CIL WCLIU 26.0 REV-INIT TOTAL CSM CRMCFARLAIO I6.0 REV-INIT TOTAL ENG ENGIRARD 18.0 REV-INIT TOTAL FFS WFSANDERS
.524.0 4
REV-INIT TOTAL HJC JLCOLEY 25.0 i
REV-INIT TOTAL JHO JRHARRIS 50.0 REV-INIT TOTAL JRR JFROGGE 22.0 REV-INIT TOTAL LHJ LHJACKSON 15.5 REV-INIT TOTAL MNH DOMUNT 28.0 REV-INIT TOTAL NGM N pfRRIWEATHER 30.5 REV-INIT TOTAL RHR RWWRIGHT 33.0 REV-INIT TOTAL TDG TDGIB80NS 2.0 4
ACT-CDDE TOTAL 739.0 i
APP ROUTINE INSPECTION PREPARATIOst REV-INIT TOTAL AER ABRUFF S.0 REV-IMIT TOTAL CIL WCLIU 4.0 REV-INIT TOTAL CSM CRMCFARC.%$
4.0 i
REV-INIT TOTAL ENG ENGIRARD 7.0 l
REV-INIT TOTAL FFS WFSANDERS 42.0 REV-INIT TOTAL GFH GAMALLSTROM 24.0 REV-INIT TOTAL HJC JLCOLEY 6.0 I-I 4
4
_m 09/20/84 U.S.N.R.C. MANPOWER SYSTEM
' PAGE '8'2 i
REGULAR MAN HOURS EXPENDED FOR THE SELECTED DOCKETS i
FOR FISCAL YEAR '34 THRU 06/23/84 REGION II - OL REVIEW t
05000424 VOGTLE 1 REVIEWER NAME OF REGULAR INITIALS REVIEWER HOURS.
APP-ROUTINE INSPECTION PREPARATION ~
REV-INIT TOTAL JHO JRHA;RIS REV-INIT TOTAL LHJ'
.LHJACKSON.
22,0 3.0 REV-INIT TOlAL MNH PONUNT..
8.0
'REV-INIT TOTAL PEK WPKLEINSORGE 2.0 REV-INIT TOTAL RHR RWRIGHT 16.0 REV-INIT TOTAL TDG.
TDGISBONS 12.O ACT-CODE TOTAL 158.0 ARD REACTIVE DOCUMENTATION REV-INIT TOTAL AER ABRUFF 10.0 REV-INIT TOTAL AFT
-A TILLMAN 12.0 REV-INIT TOTAL CIL WCLIU-25,0-REV-INIT TOTAL ENG ENGIRARD 4f. 5 dEV-INIT TOTAL JRR JFROGGE 2.0 4
. REV-INIT TOTAL JWL JBLANKFORD 2.O.
REV-INIT TOTAL NGM N MERRIWEATHER 6.0 REV-INIT TOTAL WJT WJTOBIN 2.0 ACT-CODE TOTAL 108.5 ARI REACTIVE ON-SITE /OFF-SITE INSPECTION i
REV-INIT TOTAL AER A8 RUFF
. 4.O' REV-INIT TOTAL AFT A TILLMAN 16.0 REV-INIT TOTAL CIL WCLIU 4.0 REV-INIT TOYAL EHG EHGIRAND 26.0 REV-INIT TOTAL JHO JRHARRIS 33.0 REV-INIT TOTAL JRR JFROGGE 3.6 REV-INIT TOTAL MNH M) HUNT 4.0 REV-INIT TOTAL NGM N MERRIWEATHER 32.0" 4
REV-INIT TOTAL RHR RWWRIGHT 8.0 1
REV-INIT TOTAL TDG TDGI880NS 10.0 REV-INIT TOTAL WJI WJTO8IN 9.0 ACT-CODE TOTAL 154.0 ARP REACTIVE INSPECTION PREPARATION REV-INIT TOTAL AER ASRUFF 15.0 REV-INIT TOTAL ENG EHGIRARD 18.0 REV-INIT TOTAL PEK WPKLEINSORGE 2.0 l'
1 5
~_
2 4
-09/20/80 U.S.N.R.C. MRMPOWER SYSTEM
' PAGE 83 :
REGULAR MAN HOURS EXPENDED FOR THE. SELECTED DOCKETS FOR FISCAL YEAR '84 THRU 06/23/84 REGION II - OL REVIEW 05000424 VOGTLE 1
=
-_ ___ __- __- =- -_
' REVIEWER NAaE OF REGULAR l
INITIALS REVIEWER HOURS
__ = --.--------------------------------------------------------------------------------------
ARP REACTIVE INSPECTION PREPARATION -
ACT-CODE TOTAL
. WJTOBIN
'4.0 REV-INIT TOTAL WJT 39.O'
- AS1 REV-INIT TOTAL FFS
.WFSA MERS
.0 3 -
ACT-CODE TOTAL
.0 AT INSPECTION-RELATED TRAVEL REV-INIT TOTAL AER ABRtSF
' 5.0 i
REV-INIT TOTAL CIL WCLIU 7.0 5
REV-INIT TOTAL CSM' CRMCFARLA W 4.0 i
REV-INIT TOTAL EHG EHGIRARD 7.0-REV-INIT TOTAL FFS WFSANDERS 4.0' REV-INIT TOTAL HJC JLCOLEY 7,0 REV-INIT TOTAL JHO JRHARRIS 17.0 REV-INIT TOTAL
'JRR JFROGGE J.O REV-INIT TOTAL LHJ LHJACKSON.
"J. 5 -
REV-INIT TOTAL MHH DOHUNT 4.0 REV-INIT. TOTAL NGM N MERRIWEATHER 15.5 i
REV-IhIT TOTAL RHR RWWRIGHT-Y.0 REV-INIT TOTAL SEG S GUENTHER.
R.O REV-INIT TOTAL TDG TDGIBSONS 4.0 REV-INIT TOTAL WJT WJTOBIN 10.0 ACT-CODE TOTAL 107.0 1
].
BB SALP i
REV-INIT TOTAL AER A8 RUFF 1.0 REV-INIT TOTAL ENG EHGIRARD I.O REV-INIT TOTAL JHO JRHARRIS 4.0 ACT-CODE TOTAL 6.0 BC EP LICENSING REVIEWS REV-INIT TOTAL FFS WFSANDERS 3.0
('
ACT-CODE TOTAL 8.0 1
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09/20/24
~ U. SIN.k.C.' MANPOWER SYSTEM PAGE 54 REGULAR lenN HOURS EXPE90ED FOR THE SELECTED DOCKETS FOR FISCAL YEAP '34 THRU 06/23/84 4
RECTON II - OL REVIEW 05000424 VOGTLE 1
-_=___..____........_____.......__.s REVIEWER seAME OF REGULAR ~
HOURS
~ INITIALS REVIEWER i
SD2 RESPONSE TO EVENTS / INCIDENTS
~
i REV-INIT YOTAL BDH BLHALL 2.0.
4 REV-INIT TOTAL JIE J ENNIS 2.O' j
ACT-CODE TOTAL' 4.0 j
BE TECHNICAL SUPPORT FOR INVESTIGATIONS' i
REV-INIT TOTAL AFT A TILLMAN
- 4. 0 -
4.
REV-INIT TOTAL BAU
.B URYC
.O REV-INIT TOTAL CIL.
WCLIU
,22.0 I
REV-INIT TOTAL ENG ENGIRARD 74.0 1
REV-INIT TOTAL
'FFS WFSANDERS 14.0 REV-INIT TOTAL GET GATODO 1.0 REV-INIT TOTAL JWL JBLA8eKFORD 2.0 REV-INIT TOTAL seGM N DERRIWEATHER I.O
?
ACT-CODE TOTAL' 118.0 BH QUALITY ASSURA8eCE REVIEWS REV-INIT TOTAL FFS WFSANDERS 3.0 -
j REV-INIT TOTAL LHJ LHJACKSON
. 21.0 IR.O j
ACT-CODE TOTAL 9
4 SJ -
ALLEGATION FOLLOW-UP l
t REV-INIT TOTAL AER ABRUFF I4.0 REV-INIT TOTAL ENG ENGIRARD
.O.
)
REV-INIT TOTAL FFS WFSANDERS 9.0 t
i REV-INIT TOTAL JRR JFROGGE 6.0 i
REV-INIT TOTAL BeGM N MERRIWEATHER 32.0 j
ACT-CODE TOTAL 111.0 s
't
~
seRR seRR TAC-RELATED ACTIVITY r";
4t 24.0(
_ y )'M i
EACOOK REV-INIT TOTAL EHC I'p i
REV-INIT TOTAL LTN TLseORRIS 18.0.
f~,~,g-y ps#'
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REV-IMIT TOTAL SEG S GUENTHER 10.0 ACT-CODE TOTAL 50.0 i
DOCKET 8eO TOTAL 1.971.5 i
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09/20/34 REGULAR MAN HOURS EXPENDEDU.S.N.R.C. MANPOWER SY 05000424 REGION II - OL REVIEW FOR ELANK ACTIVITY CCOES F M
VOGT OR FISCAL 1rEARFOR THE SELECTED DOCKET
..._................LE1 dF
"$4 THRu 06/23/84 PAGE 8 REVIEWER....................
.............. INITIALS EAsf OF 131
............... REVIEWER REV-INIT TOTAL POWER FACILITY INITIAL E REGULAR PA-NUM TOTAL XAMS HOURS EHC 1322 EACOOK REV-INIT TOTAL POWER FACIL. REQ *AL. EXA4 16,0 PA-sum
....e TOTAL J
LTM 16.0 134 TENORRIS REV-INIT TOTAL CERTIFICATION EXAMINATIO frEV-INIT TOTAL YOTAL.
NS 18.0 Y )
PA-NW TITLE SEG EACCOE t u g#
16.0 LOCKETNO TOTAL EHC TOTAL g.
S GUENTHER
(
8.0
>* 4 10.0 14.0 7
50.0 2.584.0 9
-d n
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1
)lSTRIBUTION:
i
'DR i
LPDR 4
II N ^?.ual Manpower File 4
UAN 171985 RMDiggs, LFMB CJHolloway, LF2 i
- i Reg. Docket File
]
i Docket Hos. 50-390 DWeiss,LF2 i'
and 60-391 LFMB Reactor File LSolander, NRR l
MKaltn.an, NRR LFN2 R/F Tennessee Valley Authority-ATTH: Mr. H. G. Parris j
Hanager of Power 500A Chestnut Street Tower 11 Chattanooga, Tennessee 37401 i
Gentlemen:
As you are aware,10 CFR 170 of the Comission's re1olations for license and inspection fees was revised effective June 20, 1984.
Section170.12(b) of the revised rule pmvides that for applications for permits, licenses, facility reference design approvals, and special projects which have been on file with the Comission for review for six months or longer, the first bill for accumulated review costs would be sent to the applicant at the time the rule beconses effective and thereafter at six-month intervals-or when the review is conpleted, whichever is earlier. The first bill for the operating license (OL) review will include applicable professional l
staff review time expended through June 23,1984, and contractual support services expended to May 31,1984.- Subsequent bills covering six-month reviews will be issued approximately ninety days after the end of_ each j
six-nonth period which closes in December and June of each year.
Consistent with the requirements of 10 CFR 170.12(b), we have completed the cost analysis for the Watts Bar 1 OL application review for the period specified above.. The cost through that period for Watts Bar-1-is $3,324,761.
The cost of the OL review through June 23,1984 exceeds the maximum fee of
$3,077,400 as stated in 10 CFR 170.21. Accordingly..$3,077,400 is the maximua, amount that may be assessed for the. OL review under 10 CFR 170 as revised June 20,1984. The Office of Resource Management has been notified to bill your Company $3,077,400 for Watts Bar 1.
When making payment, please make reference to the invoice number on your bill.
Enclosed is a copy of the revision to Part 170 as.sent to all applicants and licensees on May 24, 1984.
Sincerely.
l Nnh Sf;Md Fy,7 Wm. O..N:;l. r gIOM William O. Miller, Chief License F,ee, Management Br@typ/\\
numiMiawabswi-\\w viv e vi
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UNITED STATCS A
NUCLEAR REGULATORY COMMissl0N g.
WASHINGTON, D. C. 20666 Docket No. 50-390 UAN11 g MEMORANDUM FOR:
Files THRU:
William 0. Miller, Chief. License Fee Management Branch, ADM FROM:
C. James Holloway, Jr,, Assistant Chief. License Fee Management Branch, ADM
SUBJECT:
Watts Bar 1 OPERATING LICENSE REVIEW COSTS 10 CFR 170 of'the Comission's regulations for license fees was revised effective June 20, 1984.
Section 170.12(b) of the revised rule provides that for a)plications for operating license. (OL) review which have been pend-ing with t1e Comission for six months or longer,' the first bill for accumulated review costs would be sent to the applicant at-the time the rule becomes effective and at six-month intervals thereafter until the review is completed, whichever is earlier.
The first bills for OL review will include applicable professional staff review time expended through June 23,1984, and contractual sup) ort services expended to May 31,1984.
Subsequent bills covering six-monta reviews will be issued approximately ninety days after the end of each six-month period which closes'in December and June of each year.
In accordance with Section 170.12(b), we have reviewed the cost incurred by the various program offices directly involved in the review of the Watts Bar 1 o)erating license. Attached is a summary of the review costs as well as t1e sup)orting documentation from the program offices. The attachment shows t1at a total of $3.324,761 was ex) ended through June 23,1984 for the'.
OL review.
The cost of the OL review t1 rough June 23, 1984 exceeds the maximum fee of $3,077.400 as stated in 10 CFR 170.21.. Accordingly, $3,077,400 is -the maximum amount that may be assessed for the OL review under the 10 CFR 170 as revised June 20,1984.
However, in the event that the regulation is subsequent--
ly revised and the ceiling is raised to a higher number or eliminated before-Watts Bar 1 is licensed, then additional fees could be assessed up to any new ceiling or-for the full-cost if the ceiling were eliminated. A refund would be made if the amount in the rule at the time the license is issued is less than $3,077,400.
0 W
t 9/ James Hol oway, Jr.,
ssistant Chief g M'p License Fee Management Branch Office.of Adminstration
Enclosure:
Sumary of ' costs;and supporting.
documentation
Tennessee Valley Authority Operau.ig License Review Costs Through vune 23. 1984 FACILITY:
Watts Bar 1 p0CKETNO.!
50-390 Costs Per Professional Pregram Office Professional Staff-hours staff-hour Contractual Total Review
, Staf f-hour
_ Expended
__ Costs
__ Costs Costs 1.
$39 48,200.7
$ 1,879,827
$ 409,908 2,289,735 2.
IE-HQ 36 677.0 24,372 24,372 3.
REG 10H5 36 26,990.8 971,669 971,669 4.
$0 466.0 23.300 23.300 50 NMSS 38 412.75 15,685 15,685 Total Cost: $3.324,761 Y
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septembegsg(pfs P257 MEMORANDUM FOR:
Patricia G. Norry, Nr o
Of fice of Administration FROM:
Jesse L. Funches, Director Planning and Program Analysis Staff Office of Nuclear Reactor Regulation SUBJEC1:
30 CFR 170 N01[ Or FINAL RULEMAKING - REQUE51ED LICENS[
FL[ INFORMATION Enclosed is the NRR response to your memorandun of July 3, 1984.
Our response includes:
- 1) a listing of the dockets for which we have assembled data; 2)by docket, indicating regular and non regular hours, and any he the professional staff hours that have been reported to the RAMS
- system, effort reported, covering the period between Construction Permit issuance and Junt> 23, 19B4; 3) a listing of plants that have had contested hearings;
- 4) a listing of casework plants that have associated PRA review effort, including hours reported and asse:iated FIN nunbers; 5) a listing of all identified contract effort for all dockets that have specific technical assistance charges, with PRA review effort charges identified; and 6) a 4
listing of professional staff hours reported and contract costs for topical j
reports.
Not included are contract costs for FINS covering one or more non-docket specific topical reports for the period 10/1/83 - 6/30/84, which will be forwarded to you under separate cover when sof tware fixes to the TAPS $ system are completed.
l is a list of all OL applications currently on file and applications for standard design reviews that we have gathered the information you requested.
For EPRI SDA and FNP 3-8, the Project Managers have decided that these projects are not fee-recoverable. indicates professional staff hours for each dodet that was reported in the RAMS system from the date of the Construction Permit issuance through Junt 23, 1984.
Regular and non regular professional staff hours are indicated.
From the total hours shown, hearing effort, is broken out.
To the extent feasit'lt, date on hours that were reported have been reviewed by the Project Managers.
However, in some instances where there are hours f
charged many years ago, there is no basis for reviewing hours reported, and these hours are included as they are reported in RAMS. indicetes a listing of plants that have had contested hearings.
M
)
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.t.
Inclosure 4 is 9 listino of Casework plants that have associated PRA review ef fort, showing professional staf f hours reported in RAMS and any associated FIN numbers.
[nclosure 5 lists all identified contract effort for all dockets that have
~
specific technical assistance charges, the first part indicates charges through September 30,1983.
The printout indicates any associated charges by.
docket for the period October 1,1983 through May 30,1984.
As you are aware, technical assistance charges are reported on a monthly. basis, not weekly, therefore these charges are through May 30,1984 instead of June 23, 1984 PRA review effort is identified.
. is a printout listing professional staff hours reported and contract costs associated with topical reports submitted titer March P3, 1978 and still being reviewed through June P3, 1984 Contract costs for non docket-specific topical reports for the period 10/1/83 3 6/30/84' are not available at this time. They will be submitted at a later date.
Please contact Lars Solander of my staff if you have any questions.-
e Jesse L. Funches, Director Planning and Program Analysis Staf f Office of Nuclear Reactor Regulation
Enclosures:
As stated 4
4 nn m-,
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,:n
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P, a
- 2 M U S*
d.! hll nwe
- ~,., -
Manpower Hours Hearing Charges Out ef P
Plant Docket No.
Reg.
Noa Req. Hrs.
Total Reg.
Non Reg. Hrs 20,156.1 777.1 20,933.2 90 0
Nine Mile Pt. 2 50-410 Palo Verde 1 50-528 i
31.166.3 1,833.6 33.050.1 4 94.5 44.5__
LJ Palo Verde 2 50-529 l
1,995.6 60.8 2,056.4 872.8 11 alo Verde 3 50-530 1
210.8 4
214.8 6
0 50-440 34,003.7 1,716.8 35 720.5 4,052.2 119.5 gPerry 1 Perry 2 50-441 342.0 14.5 356.5 16 0
t River Bend 1 50-458 23,9/0.3 832.1 24,802.4 54 0
River Bend 2 50-459 891.5 39.0 930.5 0
0 g / 5eabroot 1 50-443 43,444.4 z,94 C 45,389.5 2,355.5 223.0 N Seabrook 2 50-4-44 1.687.9 100.5 1.788.4 241.0 37.0 q / hearon Harris 1 50-400 32,456.5 1,133.9 33,595.4 1,631.0 156.0 S
N5hearon Harris 2 50-401 425.0 4.5 429.5 0
0 QO -Shoreham 1 50-322 i
68,052.2 1 4,055.1 12.118.3 15,365.8 1.017.9 South Texas 1 50-498 26 /55.3 1.2Z3.1 ZI,979.4 8,700.5 394T b
South Texas 2 50-499 3.794 33 3,827 2.202 17 Vogtle 1 50-4z4 14,314.3
/4s.b 15,zbJ.1 409 IFE---
Vogtle 2 50-425 216 9.5 225.5 0
0 LIJ-WaterfoM3
- ~ - - ~ ~ 50-382~ ~~' ~~
~
41,01 Q
~ ~3,894 7 44 912.7 877.8 72
' p Wa tts Ba r 1 SU-J9U
[so,tuu.//
4,554.b bl,Usb.J ab5 9
Watts 8ar 2 50-391 Z,033.7 39.6 2,073.3 0
0 Westinghouse 50-601 1,zus ss 1,263 u
o Wolf Creek 1 50-482 20.173.7 1,163.9 21,337.6 458.3 31.4 h
- WPP55 1 50-4t,U i
b,4/U.S 229.2 5,b99./
bzU.S 19 7 P&Rs 1 50-508 i
zz,961 1,z49.J z4,z10.3 1,064.5 109 Yellow Creek 1 50-566 1.645 116 1,761 81 3
9 d
- 9 g.
4&.-
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Plants Which Have Iled Contested Hearings flLn},
Docket No,s
" fron 1 & 2 60 454, 455 stewb6 3 4 2 60-433, 414 linton 1 60-461 i
4 omanche Penn 1.4 2 60-446, 446 C
4 4 16010 Canyon 2 60 323 0
- eral 2 60 341
- 1.imerick 1 4 2 60 352, 353 4 erble Hill ) 6 2 60 646, 647 Midland 16 2 60 329, 330 4ft10 Veroe l', 2, 3 60 628, 629, 530
- Terry 3 & 2 60 440, 44}
MeeDrook 16 2 60 443, 444 M inetron Harris 1 & 2 60 400, 401 6Thorehem J 60 322
% terford 3.
50 382 NolfCreek1 60 482 StWPP55 3 60 460 Y.&\\ {\\s\\ +, Coul di~) C M L
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Plant Docket No.
Total Cost PRA Portion
~ Shoreham 1 50 322 781,001 "C'
South Texas 1 & 2 50-498/499 497,839.89
- 0 7((M 'S'"
Unit 1 160,545.24 Unit 2
__ 55.128.24 rr, e o Total all costs 713.513.37
+,,, u ir.,,,,, n Vogtle 1 & 2 50 424/425 54,303
-0
- "S' Unit 1 13,109
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Unit 2 0
Total all costs 67,412 v.,m ev,,s, Waterford 3 50 382 1.283,157.51
-O'-
WeWslar 1 IT-"
50390/39i 358,439.75
- C'
- ' 'l'.,7,',,
[9 Unit 1 103,189.00
,j,',7 l-Unit 2 15.200.00 M a**
Total all costs 476,828.76 tri.at (,,* A u Westin9 house 50-601 32.784 Wolf Creek 1 50-482 534,506.36
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WPP55-1 50 460 39,634 0-WPP55-3 50 508 127,289.92 Yellow 3 eek 1 50 566 None _
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.... e Y'..'y, BILL. JR COLLECTION ce.,
D0152 est (Mtcas eAe Asts to tHa t> s hvet,t An meoutAtome couvissioN AND uAe610 MH8 J
U.8, NUCLE Al REGULATORY COMMi$$10N I/II/
/
f OFFICE OF RESOURC[MANA0tMENT D ETDdlO'T3 i
Olvisl0N OF ACCOUNflNO AND FINANCE ML 8
VyASHINGTON,DC 20646 UC 8 ktf NV*8 t h M 8MI*f'l I
Tot litiIhiivCI NVVeI G epl84 We/
Tennessee Valley Authority h
I Attn: Mr. H. G. Parris con, cv, Manager of Power um 500A Chestnut Streete Tower !!
Janet M. Rodriguez Chattanooga, TN 37,401 3ri.cewour gpwmta j
soi 492-4200,
DE SC RIP, ION AMOUNT Operatin details)g License Review for Watts Bar 1 (see attached for
$3,077.400.00 -
[
b
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p.,
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' c, 23 w
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En AMOUNTDUt
$3,077.400.00-TERMS.
Interest will accrue from the bili date et the annuet rete et 9.00 pod in full by the payment due date.
%, excepi ihai no interest,viii be cherped it the amouni due is
~
NOTE.
The NRC debt collection reputations are found in 10 CFn 15 sw are based an the Federal Clelms Collection Ac Collection Act of 1982. If there see any questions about the enletence or amount of the debt, refer to these re e
the Individual named above. The revocation of a license does not wolve or offect any debt then due the NRC from the lice PRESENT AND SEPARATED EMPLOYEES:
The etteched Notice of Due ProcessIllghts applies to trth current end former employees.
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