ML20040A576

Forwards Info in Response to Concerns Identified by Licensee Qualification Branch in Suppl 1 to SER & ACRS Recommendations in 811020 Ltr to Commissioner Palladino

ML20040A576
Person / Time
Site:	Grand Gulf
Issue date:	01/18/1982
From:	Dale L MISSISSIPPI POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0831, RTR-NUREG-831 AECM-82-12, NUDOCS 8201210258
Download: ML20040A576 (71)

Text

MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi M 4HanddB P. O. BO X 1640, J AC K S O N. MIS SIS SIP PI 3 9 2 05 January 18, 1982 ['II(

now an numcnon t4 pantw nr Y \',\g U. S. 1:uclear Regulatory Comnission Office of 1;uclear Reactor Regulation 4-j ,y!/' 'l ' 7 m , I_,

'< ' C" Washington, D. C. 20555 Vi Attention: Mr. Harold R. Denton, Director

Dear Mr. Denton:

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SUBJECT:

Grand Gulf I;uclear Station Units 1 and 2 Docket IIo n . 50-416 and 50-417 Fi l e l'o . 0260/L-334.0/L-350.0 Response to Concerns of Licensee Qualification Branch AECM-82/12 The enclosed infornation represents Mississippi Power & Light's (MP&L) responce to various concerns identified by the Licensee Oualification Branch in Suppicaent tio . I to NUREG 0831, Grand Gulf !:uclear Station Safety Evaluation Report. This letter also addresses certain recomnendations made in this area by the Advisory Comnittee on Reactor safeguards (ACES) in the ACRS letter, Mark to Palladino, dated October 20, 1981.

1. Corcern:

ta Figure 13.1-3 of the FSAR the Operations Superintendent appears to report to both the Assistant Plant Manager and the Nuclear Support Manager.

Rtuponse:

Normally the Operations Superintendent reports to the Assistant Plant Manager and Plant Manager. In the event both of these managers are temporarily incapacitated, the Operations Soperintendent reports to the Nuclear Support Manager. This line of succession is consistant with FSAR Subsection 13.1.2.2.1. Figure 13.1.3, (Attachment 1), has been nodified to renove the ambiguity.

J. Concern:

TSe staff requires that the applicant provide one or more staff nenbers with substantial BWR experience reporting to the Senior Vice President - Nuclear for a ninimum of one year following fuel load. In AECM-81/284, however, the applicant states that such a person will be retained until 100% power is reached and will report to the Assistant hc0l 5

Vice President - Nuclear Production.

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820 1210 ABS Member Middle South Utilities System

AECM-82/12 MISSISSIPPI POWER & LIGHT COMPANY Page 2

Response

MP&L agrees to retain the additional staff member for a minimum of one year following fuel load. MP&L considers it more appropriate that r;c?.d staff member report to the Assistant Vice President - Nuclear Production as the latter individual is the corporate official closest to day to day upper management decisions involving plant operations. The staff member will be available for consultation with the Senior Vice President-Nuclear as necessary. Mr. James Groves has been selected to fill this position. See Attachment 2 for his resume.

3. Concern:

There is no indication of the professional experience required of the individual enginecro in the Operational Analysis Group.

Response

FSAR Subsection 13.1.1.1.3.1.4, (Attachment 3), has been modified to reflect that cach individual will have a minimum of two years professional experience in the area of his specialty.

4. Concern:

As required by NUREG-0737, Action Item I.C.5, the applicant should demonstrate how industry operational experience information is coordinated and distributed throughout the applicant'L organization.

Response

The requirements of NUR'G-0737, Action Item I.C.5, are addressed in a procedure that is part of the corporate administrative guidelines and policies, Attachment 3A. This procedure provides for overall control, distribution, and review of <locuments containing plant operating experience.

5. Corcern:

The organization and procedure description of the Safety Review Committee indicates the meetings of the committee could be by conference call rather than face to face. In Subsection 6.5.2.10 it is not cicu who approves the records.

Response

Section 6.5.2 of the Technical Specifications, (Attachment 4), has been revised. Subsection 6.5.2.5 ha^ been revised to clarify that conference calls may be used for emergency meetings. In 6.5.2.10 approval of records is a function of the Assistant Vice President -

Nuclear Production.

6. Concern:

The applicant does not state the qualifications that are required ,

for an independent verifier. l l

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AECM-82/12 MISSISSIPPI POWER & LIGHT COMPANY Page 3

Response

Administra*tve procedure 01-S-06-2, Conduct of Operations will be revised to cla? ify the qualifications required of independent verifiers.

A description of those qualifications is provided below. The approved change notice is included, Attachnent 4A.

" Independent verifiers shall be classified to a position higher than Trainee. This position will be in accordance with certification per ANSI 18.1-1971. Independent verifiers shall be of Journeyman level for their respective maintenance disciplines; eg., engineer, a person certified to perform specific duties in an engineering discipline, a qualified health physicist or a chenist per the above noted ANSI requirements. Operations personnel shall be either licensed operators or qualified Nuclear Operator B's for the system or systems being independently verified."

7. Concern:

Additional information is required regarding coverage on each shift with personnel having adequate BWR experience. Anderson and Warner qualify for two of the shifts but information is needed that the other three shifts will also be covered, as well as the duty locations of these individuals and their qualifications.

Response.

MP&L will assign an individual to each shift, excluding Anderson's and Warner's shifts, who was previously licensed as an SRO on a BWR. These individuals will normally reside in the control room area during Operational Conditions I and II, but will not be restricted from checking on equipment in the other buildings. During transients they will report to the control room in order to advise the Shif t Supervisor.

As noted in the statement of the NRC's Concern, Anderson and Warner have adequate experience to satisfy the requirement for an individual with substantive BWR operating experience on each shift. Therefore, an experienced advisor will not be provided for their shifts. Copies of resumes of E. M. Dugger, U. S. liiff and P. Wolfinger are provided as Attachment 5 to this letter. These personnel will fill the positions of BWR experienced shift advisors.

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8. Concern:

Provide additional assurance that the pipeline of trainees to Reactor Operators will provide for adequate shift coverage in the future, j allowing for exam failures, attrition and other contingencies.

l Response:

The training progran is designed to take an entry level person (unexperienced) through all requirements for NRC licensing in approximately three years as follows:

" - - m AECM- 42 /12 MISSIS'JIPPI POWER & LIGHT COMPANY Page 4

- 1 year to complete qualification as an Auxiliary Operator, Nuclear (AGN)

- 1 year as an AON to complete requirements as a Nuclear Operator B (NOB)

- 1 year as a NOB to complete training toward NRC license (R0 level)

One additional year at the R0 level would be required to be licensed at the SRO level.

Currently there are sixteen Operations Section personnel who have taken the SRO license exam and an additional eleven personnel who have taken the R0 license exam. This should be adequate personnel (not including instructors) to provide five fully staf fed shif ts.

In addition, we have four personnel who will complete training requirenents for NRC licensing (at the R0 level) in May or June of 1982, five more will complete training requirements for RO licensing in December, 1982 and twelve more in June, 1983.

Thereafter, we intend to put five trainees into the " pipeline" each year so that we will have adequate reserve for attrition. All applicants are screened and only those who appear to have the potential skills, aptitudes and character and psychological traits necessary for SRos are selected. .

9. Concern:

Information has been submitted concerning the tafety related responsibilities of the shift superintendent. Provide a detailed description of his other administrative responsibilities and which ones are delegated te other nhift pereennel freeing him to concentrate on safety related problems.

Response

Provided as Attachment 6 is a listing of the administrative responsibilities of the shift superintendent. Those duties that will not be delegated are designated with a "P"; those that will be delegated, with a "D". The shift superintendent will not be distracted by strictly administrative activities . Other routine and non-routine administrative duties, such as overtime scheduling, arrangement for meals and labor negotiations, will normally be dealt with by other plant staff members as indicated:

1) Time sheets, shift schedules and vacations-Operations Assistants

2) Offsite call-ins and approval of overtime meals-Shift Supervisor

3) Maintenance of overtime meal system-Operations clerical personnel, and

4) Normal unien relations-Operations Superintendent.

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AECM-82/12 MISSISSIPPI POWER O LIGHT COMPANY Page 5

10. Concern:

The overtime procedure in Administrative Procedure 01-S-06-2 is satisfactory; however, the overtime procedure in 02-S-01-4 is not consistent with Procedure 01-S-06-2.

Response

Procedure 02-S-01-4, Attachment 6A, has been revised to be consistent with 01-S-06-2.

11. Concern:

The Plant Safety Review Committee Procedure requires revision to require that a quorum shall consist of the chairman and four other members.

Response

Procedure 01-S-01-il states that a quorum shall require the presence or the polling of five PSRC members or alternates, of which one must be either the chairman or vice chairman and no more than tv.o may be alternates.

Should the procedure require the chairman to be present at all meetings, the PSRC would lack flexibility and be unable to make important decisions it. his absence.

12. Concern:

The applicant should show com'liance p of fire brigade training with 10CFR Appendix R.

Response

FSAR subsection 13.2.4.1, Attachment 7, has been revised to show compliance with Appendix R.

ACRC Concern:

The ACR'S, in the letter referenced earlier, offered certain tecomeendations to Chairman Palladino in regard to the compoeition of the Safety Review Commit tee. Consistent with that recommendatior, MP&L has selected two additformil personnel for membership for that comaittee. Neither of the new members are in the employment of or are connected with MP&l. in a r. - way. These new members are Dr. John I. Paulk and Mr. Ellory llammond.

Dr. Paulk is the former hend of the Department of Nuclear Engineering, Missisnippi State University, and now the Associate Dean for Research in the College of Engineering of that University, serving as the Director of the Engineering and Industrial Research Station. Mr. llammond has formerly served as Plant Manager for an operating BWR (Duane Arnold) and is currcntly the' plant manager for a BWR-6 under construction (River Bend). Resumes sfor both consultants are provided for your information.

Also included is the' resume of Mr. Jackson B. Richard who represents Middle South Services, Inc. en the Safety Review Committee. See Attachment 8.

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AECM-82/12 MISSISSIPPI POWER & LIGHT COMPANY Page 6 The resume of. Johnny Pinto, the new Manager of Nuclear Plant Engineering; Steven P. Hutchins. Principal Engineer Electrical Group; Robert C. Fron, Principal Civil Engineer and Milton L. Jones, Engineering Services Supervisor are enclosed, Attachment 9.

Yours t,ruly, 5L. F. Dale

[ Manager of Nuclear Services PJR/JDR:ph Attachment cc: Mr. N. L. Stampley (w/a)

Mr. R. E. McGehee (w/a)

Mr. T. B. Conner (w/a)

Mr. G. B. Taylor (w/a)

Mr. Richard C. DeYoung, Director (w/a)

Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l

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Attachment 1 1 NUCLEAR PLANT MANAGER AECMLB2/12

OSRO I

I I ASSISTANT PLANT MANAGER NUCLEAR SUPPORT MANAGER

• SRO *SRO l

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OPERATIONS SUPERINTENDENT SRO I

g RADWASTE SUPERVISOR OPERATIONS ASSISTANTS l NUCLEAR (1) NLR (2) SRO j SHIFT SUPERINTENDENTS

] (5) SRO

____________._q SHIFT SUPERVISORS SHIFT (5) SRO TECHNICAL ~

ADVISORS a

(5)

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RADIATION PROTECTION REPRESENTATIVE (5)

I . I NUCLEAR NUCLEAR AUXILIARY 4

OPERATORS OPERATORS OPERATORS R0"A" NLR"B" NLR (10) (10) (20)

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NOTES: SRO-Senior Reactor Operator R0-Reactor Operator NLR-No License Required (X)-Number of Plant Personnel assigned to this position

-- -Shift Technical Advisor communicates with SRO'S but reports to the Reactor Engineering Supervisor i

• -The Plant Manager, the Assistant Plant Manager, and the Nuclear Support Manager are trained to SR0 level in addition to those in the operations organization

...-Temporary line of succession in event of incapacity of both the plant manager and Assistant Plant Manager. See Subsection 13.1.2.2.1 MISSISSIPPI POWER & LIGHT COMPANY )

GRAND GULF NUCLEAR STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT l

l GGNS UNITS 1 & 2

[ PLANT OPERATIONS ORGANIZATION ONE UNIT OPERATION FIGURE 13.1-3 A21ph1 I

Attachment 2 GG AECM- 82 /12 FSAR Resume No. 73 Name: James F. Groves Birthdate: 1925 Formal Education and Training:

University of Tennessee and Career Institute of Chicago, Engineering, Mathematical Analysis and Economics, 1961-1966 6 months on-the-job reactor operating experience and training at Oak Ridge National Laboratory 4 months on-the-job reactor operating experience and training at Consolidated Edison's Indian Point Nuclear Station, Unit 1

, 10 weeks Basic Reactor Technology at ECCR 1 week Simulator Training at EGCR 1 week Elements of llealth Physics 5 weeks GE-BWR Plant Technology Course 12 weeks GE-BWR Simulator plus two 1 week refreshers 135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br /> Westinghouse PWR Plant System Familiarization Course 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Onsite Lecture Program, Watts Bar Nuclear Plant I week PWR Simulator Short Course 14 other formal job-related technict i and non-technical courses including four in supervisor development and modern nanagement techniques Experience:

1951 - 1981 Tennessee Valley Authority 1951 - 1953 Participated in TVA's Student Generating Plant Operator Training Program at Hales Bar, Watts Bar, Johnsonville and Shawnee Steam Plants.

1953 - 1960 lleid, in sequence, every operating position from assistant operator through shif t supervisor during some phase of startup and subsequent operation of all ten 150 MWe pulverized-coal-fired boiler-turbo-generator units at TVA's Shawnee Steam Plant.

1954-1956 Plant Training Representative for Operators 1957-1958 Instructor for class of 22 student operators 1958 Attended Principles of Reactor Engineering seminars conducted by enginccrs and scientists from Oak Ridge National Laboratory 1960 - 1966 Served with TVA's forces at the Atomic Energy Commission's Experiruental Gas Cooled Reactor (EGCR) Project near Oak Ridge, Tennessee, certifying at the Senior Reactor Operator j level.

. 1966 - 1968 Power Plant Operatiens Specialist in TVA's Chattanooga l Corporate Office.

1968 - 1971 Operations Supervisor at TVA's Browns Ferry Nuclear Plant i during Preoperational stage.

13A-172 Clrg84

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GG FSAR James F. Groves - continued 1972 - 1976 Assistant Power Plant Superintendent at Browns Ferry during Preoperational testing of Units 1, 2 and 3, and startup and subsequent operation of Units 1 and 2. Each unit was comprised of a 3293 MW General Electric boiling water E

reactor and a 1098 MWe GE turbo-generator. Licensed Senior Operator, Units 1 and 2.

1976 - Feb. 1980 Powet Plant Superintendent at Watts Bar Nuclear Plant during preoperational pl ese of two 3411 MW Westinghouse pressurized water reactors each powering a 1218 MWe Westinghouse turbo-generator.

Feb. 1980 - Aug. 1981 On loan to Institute of 1suelear Power Operations (INPO). Served concurrently as an Evaluation Team Manager and as the Operations Department Manager.

Aug. 1981 - Nov. 27, 1981 Project Manager on Director of Nuclear Power's staff in TVA's corporate Office of Power.

Dec. 1981 - Present Theophilus, Inc. Staff BUR consultant for Grand Gulf Nuclear Station. Advises the Assistant Vice President -

Nuclear Production and other executive personnel concerning operation and technical aspects of Boiling Water Reactors.

Professional Certified Senior Reactor Operator, ECCR Licensed Senior Reactor Operator Browns Ferry Nuclear Plant, Units 1 and 2 Served on Board of Directors, Watts Bar Chapter of National Management Association, 1978 - 1979 13A-173 Clrg85

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Attachment 3 GG AECM-82/12 FSAR 13.1.1.1.3.1.4 OPERATIONAL ANALYSIS GROUP 1.0 SCOPE OF ACTIVITIFS The activities of the Operational Analysis Group are directed by the Principal Fngineer Operational Analysis. The Operational Analysis Group is responsibic for performing integrated system operational analysis and safety review in the following areas: (1) Perform evaluations of system off-normal thermal-hydraulic conditions and plant transients; (2) Investi-gate and evaluate system operational anomalies; (3) Perform independent safety reviews of equipment deficiencie?, repetitive equipment malfunctions and plant systems performance; (4) Provide technical support to the plant staff in the event of an energency; (5) Review and evaluate the applica-bility of industry and NRC informational bulletins and orders and provide appropriate responses; (6) Provide recommendations to plant and corporate nanagement on matters affecting safety and plant operation.

The resolution of safety or operational issues requiring capabilities beyond that of the Group or which may be deemed to require independent analysis may be recommended by the Principal Operational Analysis Engineer.

The Principal Engineer will also serve as a participating member of the off-site Safety Review Committee.

2.0 TECllNICAL QUALIFICATION GUIDELINES The Operations Analysis Group organization and responsibilities are within the general guidelines of NUREG-0731 (Draft Report for Interim Use and Comment) as specifically described in paragraph 1.0 above. The Group will consist of a minimum of five dedicated personnel with responsibilities and training in the following areas:

Area of Capability Training (Minimum)

. Thermal-Hydraulics B.S. in Mechanical, Nuclear or Chemical Engineering

. Core Physics and Control B.S. in Nuclear Engineering

. Plant Transients B.S. in Mechanical or Nuclear Engineering

. Reactor System Behavior B.S. in Engineering and SRO or B.S.

in Engineering and experience equivalent to an SRO In addition, each individual in operations analysis shall have a minimum of two years professional experience in the area of his speciality. Qualifica-tions of the Operational Analysis Principal Engineer shall include a minimum of an appropriate Bachelors degree and six years experience in power plant operation and/or design.

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e GG FSAR The Operational Analysis Group Principal Engineer reports to the Manager of the Nuclear Plant Engineering who reports to the Assistant Vice President-Nuclear Production.

3.0 TECilNICAL SUPPORT RESOURCES Thermal-hydraulic and transient analytical models incorporating specific plant unique mrameters will be utilized by Operational Analysis Group to identify and quantify operating safety margins during transient or off-normal plant operating and emergency conditions. The analytical and computer capabilities of Middle South Services is utilized to provide support for performing plant specific transient analyses and to respond to requests for assistance.

Scenarios which could affect the safety of plant operations or which could lead to degradation of the integrity of the fuel or cladding will be developed for the purposes of training of staf f personnel.

The Operational Analyses Group may also utilize other qualified off-site vendors, nuclear steam system suppliers, consultants, or national labora-tory staff personnel for safety related analyses and/or consultation as deemed appropriate.

4.0 SAFETY REVIEW FUNCTIONS The safety review functions of the Operational Analysis Group will include but not be limited to the following: (1) Evaluation for technical adequacy and clarity of operations procedural changes important to safety; (2) Independent safety assessment and evaluation of plant perform-ance; (3) Review and analysis of operating anomalies; (4) Perform reviews and safety related assessments of plant organizational activities as assigned by the off-site Safety Review Committee.

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Attachment 3A

• AECM- 82/12 ,

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, Proposed Revision to the Nuclear Production Policy and Organization Manual

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l. Page 12, para. 5.2.4.4 -

. -- Revise to read as shown below. .

..e 5.2'.4.4 PrincipalEngineer-Operationalhnalysis ~

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,r., b;; , , , . . - , . . . . This Principal Engineer is responsible to authorize  ;

and evaluate detailed integrated system analyses; r

-4 assessment for applicability and prmulgation for Y m

action of operating information pertinent to plant .

, safety originating both within and outside G WS; long-term availability analyses; maintenance engi- <

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j neering analyses; and radiological and chemical . I i ,, -

operational analyses. .

2. Page 22, add paragraph 8.4 as follows: "'

s 8.4 Operational Assessment Review Policy The Nuclear Production Department Operational Assessment Review Policy is included here as Appendix 8.4.

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Appendix 8.4 Nuclear Production Department Operational Assessnent Review Policy *

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- The collective operational experiences of the nuclear power production

- industry in addition to the operational experiences at Grand Gulf  ; . '2; y

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Nuclear Station are sources of information which can provide valuable .- ,

j and timely insight into areas of opera' don, plant characteristics, plant 4' ..

l design and personnel training, which might not otherwise be apparegt or [

which might not have been expected or considered. The careful and cmpetent review of such experiences as they relate to the operation of 2:

Grand Gulf Nuclear Station will serve to identify, where existing, the q u-need for corrective actions to be taken to prevent the occurrence of -

recurrence of events which could contribute to unsafe plant operation.

It is the policy of the Nuclear Production Departnent that all members 2-of the Depar'#cht nust continually consider all sources of operating .

, . experience information in the light of how each experience and the >

la s ;.b reactions to it relate to the overall safe and efficient operation of Grand Gulf Nuclear Station. To this end a formal program of controlled reviaw of applicable operating experience will be established and will ,

require the direct involvement of managenent and supervisory personnel.

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. RESPONSIBILITIES The Manager of Nuclear Plant Engineering through the Principal Fhgineer

- operational Analysis is responsible for the establishment of an

. . Operational Assessment Review Program. He will establish procedures

. , . which provide for: -

1. the collection of information concerning operational experi-gf. ,~ , ence both at Grand Gulf Nuclear Station and elsewhere in the nuclear power production industry.

. 2. the review and screening of such information for applicability

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to Grand Gulf Nuclear Station and, if applicable, the assess-ment of the effect on plant operations.

3. the controlled dissemination of such infomation to members of the Nuclear Production Department who are cmpetent to and responsible for review of the information for implication or effect on any facet of Grand Gulf Nuclear Station operations.

4. the recording, follow up and close out of any action indicated

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as required by the review.

Procedures will configured to [.,mvi e for the following elements:

1. Clear identification of organizational responsibilities for review of operational experience information, for dissemina-tion of applicable and important information to all persons who would require or consider the information useful in the perfornunce of their responsibilities, and for establishing training and/or retraining requirements.

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2. Clear identification of all steps necessary to establish and

] follow-up required actions. '

} 3. Identifica' tion of required recipients of information for ,

review or other action.

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, 4. Provision of methods to identify and quickly prcmulgate high priority infornation.

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5. Provision of methods to screen out extraneous or or uninpor-

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tant information. '

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6. ' Provision of methods to assure that conflicting or contradic-i -t 1

s tory information is identified and withheld frcm all personnel

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a i 7. Provision for internal audit of the program.

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SOURCES OF OPERATING EXPERIENCE INEDFSRTION

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1. USNBC issued documents

a. IE Bulletins ,

b. IE Circulars

c. IE Infontation Notices <

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, .h: ;e. Audits ,

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2. GGNS issued documents .

a. Incident Reports -

b. Licensee Event Reports 1

c. Nonroutine reports required by regulations

3. Institute of Nuclear Power Operation -

a. Significant Event Reports (SERs)

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b. Significant Operating Event Reports (SOERs)

c. Notepad entries

4. Equipment supplier technical bulletins and correspondence

~ 5. Miscellaneous documents, letters, memorandums l

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Attachment 4 AECM-82/12 ADMINISTRATIVE CONTROLS RECORDS 6.5.1.8 The PSRC shall maintain written minutes of each PSRC meeting that, at a minimum, document the results of all PSRC activities performed under the responsibility and authority provisions of these Technical Specifications.

Copics shall be provided to the Assistant Vice President for Nuclear Production and the SRC.

6.5.2 SAFETY REVIEW COMMlTTEE (SRC)

FUNCTION 6.5.2.1 The SRC shall function to provide independent review of designated activities in the areas of:

a. nuclear power plant operations

b. nuclear engineering

c. chemistry and radiochemistry

d. metallurgy

e. instrumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices COMP 0SITION 6.5.2.2 The SRC shall be composed of the:

Chairman: Assistant Vice President for Nuclear Production Member: Manager of Nuclear Plant Engineering Member: Manager of Quality Assurance Member: Manager of System Nuclear Operations, Middle South Services, Inc.

Member: Nuclear Plant Manager Member: Manager of Nuclear Services Member: Corporate Health Physicist Member: Principal Engineer, Operations Analysis Members: Two experienced outside consultants ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time.

ADMINISTRATIVE CONTROLS CONSULTANTS 6.5.2.4 Consultants, in addition to those already noted in subsection 6.5.2.3, shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.

MEETING FREQUENCY 6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter. The SRC may conduct emergency meetings via a conference call or other electronic means that allows open discussion between all members necessary to fulfill the requirements for a quorum. i

- QUORUM 6.5.2.6 The minimum quorum of the SRC necessary for the performance of ,

the SRC review function of these Technical Specifications shall consist of the Chairman or his designated alternate and at least 6 SRC members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.

REVIEW 6.5.2.7 The SRC shall review:

a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

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c. proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR. '

d. Proposed changes to Appendix A Technical Specifications or this Operating License.

c. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

l g. Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.

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h. All recognized indications of an unanticipated deficiency in some j i

aspect of design or operation of structures, systems, or components '

that could affect nuclear safety,

i. Reports and meeting minutes of the PSRC.

ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 The SRC shall review the results of audits of nuclear activities conducted in accordance with the MP&L Operational Quality Assurance Manual.

Audits shall be conducted ar.d results shall be reviewed in the areas of:

a. The conformance of unit operation to provisicas contained within the Appendix A. Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training and qualifications of the entire unit staff at least once per 12 months.

c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",

10 CFR 50, at least once per 24 months.

e. The Emergency Plan and implementing procedures at least once per 24 months. i

f. The Security Plan and implementing procedures at least once per 24 months.

g. Any other area of unit operation considered appropriate by the SRC or the Senior Vice President - Nuclear.

h. The Fire Protection Program and implementing procedures at least once per 24 months.

i. The independent fire protection and loss prevention inspections I and audits that shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection film.

j. The inspections and audits of the fire protection and loss prevention program that shall be performed by an outside qualified fire consultant at intervals no greater than 36 months. u AUT110RITY 6.5.2.9 The SRC shall report to and advise the Senior Vice President -

Nuclear on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

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ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records of SRC activities shall be prepared, approved, and distributed as indicated below:

a. Minutes of each SRC meeting shall be prepared and forwarded to the Assistant Vice President - Nuclear Production for approval and subsequent transmittal to the Senior Vice President - Nuclear and all members of the Safety Review Committee within 14 days following each meeting.

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._--_..__,--_....,m , . _. ._ - _ ._ ._.. .. _._. . _ _ _ _ , . m . .. , _ -

Attachment 4A i AECM-82/12 i

TEMPORARY CHANGE NOTICE COVER SHEET I i l DIRECTIVE # 01-S-06-2 TCN # 1 DATE 11/10/81 I I ITitle nn,,ai,c r nro,nt,H m I 1 I l Latest Revision No. 3 SAFETY RELATED [xx]YES ( ]NO l l l l Cancellation l 1 I I REASON FOR CHANGE: (Dc.cribe why the TCN is being issued, and if appropriate, j summartze what procedural changes are involved) i To clarify definition of Independent Verifier.

INSTRUCTIONS FOR ENTRY: In accordance with Administrative Procedure 01-S-02-2,'..

4 write the TCN Number in the lower right portion of directive's cover sheet, initial, and date. The directive shall be marked up to reflect changes stated.

CHANGES TO BE MADE: (Use separate sheet for additional writing space)

Add step 6.1.5: See attachme::t.

i j

!O l Initial Distribution: Operations Shif t Superintendent (1) ,

Control Room (1)

Of fice Services Supervisor (1)

J PSRC APPROVAL REQUIRED (yxl YES ( } NO s /

l .

IINITIAL APPROVAL / l 6~

0L(A9 lL- ,

~~/1l10l8l /?: -

/  %& 6/mA> ,i Prsparey Dat6 /Secti6n S'epv./ Supt. '

[ ate'

\ IREVIEW AND APPROVAL l

. ' -W' // ) l .a m) ///se/D l Plant Quality Date ' Nucl' ear Support Mgr. [ ate 'lI i

i l Date Date l I I I

l lPSRC FINAL APPROVALl l X. f th / 4 YUYT f'Da/e

/ T PSRC Chairman ' Da't e l

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Independent verifiers shall be classified to a position higher than Trainee.

This position will be in accordance with certification per ANS1 18.1-1971.

Independent verifier shall be of Journeycro level for their respective main-tenance discipline, engineer or certified to perform specific duties in the engineering discipline and a qualified health physiciet or chemist per the above noted ANSI requirements. Operations personnel shall be either licensed operators or qualified NOB's for the system or systems being independently verified.

1 O

O

Attachment 5 GG AECM-E2 /12 FSAR Resime No.

Name: Charles M. Dugger Birthdate:

Education and Other Training:

Hinds Junior College, general studies Southeastern Illinois College, Chemistry Major U.S. Navy Nuclear Power School Various Navy technical schools 2

Licensed Senior Reactor Operator, Brunswick Steam Electric Plant Expe rience :

1971 - 1976 U.S. Navy, San Diego, California, USS Scamp SSN (588)

Served as a member of the Electrical Division. Qualified all engineering watch stations. Served as the leading first class Petty Officer.

1976 - !980 Carolina Power and Light Company Senior Reactor Operator. Served as Shif t Supervisor in charge of both Brunswick units and as a Radwaste Supervisor coordinating process waste.

l 1980 - Present Nuclear Services, Corporation, Tulsa, Oklahoma Supervisory Service Engineer - Assigned to NSC Tulsa regional office to provide assistance to the operations and startup groups at the Grand Gulf Nuclear Station in their procedural efforts and test coordination.

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GC

! FSAR Resume No.

Name: William S. Iliff Birthdate:

Education and Other Training:

B.S., Peru State College, Peru, Nebraska BWR Technology, Mor7is, Illinois BWR Simulator, Morris, Illinois GE Dell Operations Training Nuclear Fuel Inspection Training NRC Reactor Operators License NRC Senior Reactor Operators License Experience:

1973 - 1981 Nebraska Public Power District - Brownsville, Nebraska 1973-1974 Engineering Assistant Responsible for procedure preparation and review during construction and startup of Cooper Nuclear Station. Performed engineering reviews on various systems, startup testing and vessel internal assembly, 1974-1980 Unit Operator Performed normal plant operational duties including surveillance procedures, plant startup and shutdown.

Directly responsible for control room activities and four other operators.

1980-1981 Shift Supervisor Responsible for safe and ef ficient plant operations and all activities performed on site. Duties consisted of crew leadership, administration and plant responsibility.

1981 - Present Quadrex Corporation - Tulsa, Oklahoma Supervisory service engineer - responsible for providing consulting engineering services to various utility clients in south-central U.S.

Mr. Iliff has been involved in six refueling outages, three of which were in direct charge of refueling activities.

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GG FSAR Resume No.

Name: Pete Wolfinger Birthdate: 1946 Formal Education and Other Training:

Nucicar Power Plant Operator Training. Georgia Institute of Technology BWR Simulator and SRO certification, Morris, Illinois BWR Observation Training Technical Writing, Georgia Power Co.

Line Management School Georgia Power Co.

Senior Reacter Operator SOP-2143 Certification Docket No. 55-4399 Experience:

1967 - 1979 Georgia Power Company 1967-1971 Equipment / Assistant Boiler-Turbine Operator:

j Participated in operational activitics during construction of two 500 Megawatt, "once-through," supercritical fossil fuel l units. Operated systics and control boards through flushing, preoperational testing, and the Startup Program. Operated steam driven Boiler Feed Pumps, Precipitator equipment, Pulverizers, Polishing Demineralizers, and other equipment standard to coal fired units. Also gained experience operating six other coal fired units.

1971-1973 Nuclear Plant Operator, Edwin J. Ilatch Nuclear Station:

Reviewed Piping and Instrumentation Diagrams, and Flushing prints and procedures for possible errors or operational problems Compiled " fact sheets" for Nuclear Steam Supply and balance of Plant system. Was selected to draw simplified Piping and Instrumentation Diagrams because of drafting ability. Monitored systems construction for possible operating problems and initiated design changes in areas where problems were found. Participated in writing Operating, Annuciator Response, and Emergency procedures. Promoted to Shift Foreman and obtained a Senior Reactor Operator's license before the initial fuel loading of the first unic.

1973-1978 Shift Foreman: Responsible for supervising the operation of Units I and 2 Edwin llatch Nuclear Station during flushing, j preoperational testing, fuel loading and startup testing.

! Supervised the Operating crew on shift. Responsible for clearing equipment for maintenance and outage activities.

Initiated design changes to improve systems operation in problem area. Responsible for troubleshooting immediate and potential problems requiring in depth knowledge of Plant systems and system to system interface. Established and directed a Training Program dealing with the basis of Nuclear Power Plant operation for the new Operators on second unit.

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- . _ . _ _ - ~ _. _ ..

GG FSAR Pete Wolfinger - continued Participated in writing, review, and revision of Operating, Abnormal Operating, Ar.nunciator Response, and Emergency pro-cedures. This position required obtaining a " cold" Senior Reactor Operator's license for initial fuel loading on each unit.

1978-1979 shift Supervisor: Held overall responsibility for both Nuclear units. Responsible for coordinating activities between Departments during the Startup test program, normal operation, and outages. Responsible for supervising the operation of the Radwnste facility during the startup of second unit. Made "on 3

the spot" decisions concerning Plant operation, transients, procedure and Technical Specification interpretation, and equipment problems. Supervising Plant operation during preopera-tional testing and the Startup Program required knowledge of system design, logic, and operating characteristics. Reviewed operation of Nuclear Steam Supply and Support systems to determine where design changes were necessary. This position required holding a Senior Reactor Operater's license.

1979-1980 startup Engineer: Initially assigned to the Construction Test Group with the responsibility for Flushing, Hydrostatic Testing, and Construction Assurance Testing of Primary Systems.

Later transferred to the joint startup group and was assigned as Startup Engineer for numerous systems. Responsibilities here inclinded performing Preoperational Testing and training of plant operators, mechanics, chemists, and electricians.

Participated in " Cold Hydro;" Steam Generator Hydro, and preparation for " Hot Functional."

1980 - Present United Engineers and Constructors, Inc.

1980-1981 Startup Engineer: Assigned to a 600 MWE canadian D 0 2

Candu Reactor, responsible for hydrostatic testing, flushing, and startup testing of the heat transport purification system and participated in subsequent fix. Compiled model commissioning package for the heat transport startup group. Responsible for writing commissioning reports and system documentation. Urote tests as applicable for the main heat transport system.

1981 - Present Mid Continent Systems Corporation i

Supervisory Service Engineer - provides assistance to the operations i and startup groups at the Grand Gulf Nuclear Station in their procedural efforts and tests coordination.

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Attachment 6 AECM 82/12 OPERATIONS SHIFT SUPERINTENDENT's REQUIREMENTS - Page 1 REQUIRED ACTION FREQUENCY REFERENCE 6.2.4.a Senior management representative. Has direct N/A 01-S-01-4, Rev. I responsibility for the safe, proper, and Operations Sectioi efficient operation of the station. Responsible for ensuring all station operations in accordance with operating license and Company policy.

6.1 N/A 01-S-03-3, Rev. 3 D Shall be informed of MNCR's written against MNCR's installed / operating equipment.

g Responsible for identifying training requirements N/A 01-S-04-1, Rev. O in addition to those indentified in this Licensed Opr. Quaq procedure. and Training Pro.

Responsible for identifying training N/A 01-S-04-3, Rev. O requirements in addition to those indentified in Non-licensed 3pr.

this procedure. Qual & Trng. Pro.

6.1.1 N/A 01-S-06-2, Rev. ~3 (c) Shall operate GGNS in the absence of the Conduct of Ops.

Plant Manager. Accept responsibility and operation.

Serve as the Plant Manager's direct

' > (d) management representative for the conduct of operations and haa responsibility and authority to direct all activities and personnel at GGNS as required.

(1) Protect the health and safety of the public environment.

(2) Protect the health and safety of GGNS emp1oyees.

(3) Prevent damage to CGNS equipment and Slr11CtilreS (4) Protect the physical security at GGNS.

(5) Ensure compliance with GGNS operating 1icense, p (e) Shall retain this responsibility and authority unless formally relieved of:

(1) Operating responsibilities by a Licensed Senior Reactor Operator at the direction of any of the following personnel sheuld they be senior reactor operators:

l (a) Operations Superintendent I (h) Assistant Plant Manager (c) Plant Manager

, (2) Accident management responsibilities

( as described in the GGNS Emergency Plan and Reference 3.5.

p (f) Seek the advice and guidance of the i responsible GGNS personnel in executing his 1 duties whenever in doubt as to proper course of l action affecting their responsibilities.

l

s OPERATIONS SHIFT SUPERINTENDENT's REQUIREMENTS - PAGE 2 REQUIRED ACTION FREQUENCY REFERENCE 6.1.3

[) (d) Authority to direct GCNS employees to report N/A 01-S-06-2, Rev. 3 to GGNS for response to potential and real Conduct of Ops.

emergencies, p 6.2.1 (a) (1) May be relieved of all overall m a n a g e .a e n t responsibility by only those individuals defined in 6.1.la,b,c (Plant Manager and Assistant Plant Manager).

(2) May be relieved of responsibility and a u t h o - ! f. y for the safe and proper operation of GGNS only.

(a) By nermal relief Shift Superintendent (b) Other GGNS Senior Reactor Operators (6.lle(l)).

p) 6.2.2 (a) All station operations will be controlled and/or coordinated by Shift Superintendents through the Control Room.

(b)(1)(c) May order personnel out of the control room at any time.

6.2.3 (a) Responsible for all protective tagging at GGNS with the exception of the administration building and training center.

(b) Responsible for reviewing all maintenance work orders and trouble tickets (3.19).

(c) Grant permission to release all permanently installed equipment or systems at GGNS (exclude equipment in Administration Building, Warehouse and equipment and tools used by other sections).

Must be documented. When system iu returned to service, operations personnel shall place equipment and system in operation and verify and document it is functional at acceptability.

(e) Shall ensure surveillance tests applicable to new condition when changing plant operations conditions.

6.3.1 f (c) (3) Shall approve all core alterations.

6.4.1

{) (b) Responsible for the initial assessment and evaluation of the situa? ion and will initiate the necessary immediate actions to limit the consequences of the accident and bring it under control.

i

])

6.4.2 (b) If he determines that an emergency situation l condition does exist or has potential to exist by l his judgement or emergency action levels being l exceeded, he shall: (see next page) - __

OPERATIONS S III FT SUPERINTENDENT's REQUIREMENTS - Page 3 REQUIRED ACTION FREQUENCY REFERENCE (1) Assume the responsibilities and N/A 01-S-06-2, Rev. 3 authorities of the Emergency Director. Conduct of Ops.

(2) Implement the CGNS Emergency Plan through the use o f GGNS Emergency Plan procedures.

(3) Notify the CGNS on call staff members.

(4) Call in other GGNS employees as required.

p 6.1.2 (n)

N/A 01-S-06-2, Rev. 3 Shall perform functional testing of the Conduct o f Ops.

redundant system prior to the intentional removal of any safety related system from service, following

, maintenance, it shall be functionally tested prior

, to declaring it operable.

2.4

[) lia s direct responsibility for conduct and access N/A 01-S-06-4, Rev. 1 ,

to the control room. Access and Conduct <

6.1.2 in the Control Must approve all activities which may affect plant Room i operations, except those authorized by approved procedures or instructions.

6.3.l(a) Shall restrict Control Room access to individuals responsible for operation of the plant and others as he deems necessary.

) 2.3 N/A 01-S-06-5, Rev. 1 Responsible for ensuring that all incidents that Reportable Events occur on his shift are reported in accordance with this procedure. Responsible for forwarding the Incident Report or appropriate copies for further action.

p 6.2.2 Shift Superintendent (a) Review the Incident Report upon receipt and determine if it can be categorized as an incident.

(b) If Incidient Report required, enter Incident Report in Incident Report Log, Attachment III.

Maintain Log.

(c) Complete his section of the Incident Report (d) Contact Operations Superintendent if required NRC prompt or 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification.

I (e) Contact Plant Marager or Assist Plant Manager if the Operations Supt. cannot be reached.

2.2 i) Responsible for aPProv:ae access to the Containment N/A 01-S-06-7, Rev. 1

/Drywell anytime primary containment integrity is Containment and required as specified in GGNS Technical Drywell Access Specifications. Ensure that all access to the  !

Control Containment /Drywell is in accordance with thia '

procedure.

OPERATIONS S il I F T SUPERINTENDENT's REQUIREMENTS - PAGE 4 FREQUENCY REFERENCE REQUIRED ACTION 6.3.2 01-S-06-7, Rev. I h(a) Determine if plant status and conditions in N/A Containment and the Containment are such that Containment entry is Drywell Access permissable. Control (b) Obtain following information on persons entering containment and record the appropriate information on the Containment /Drywell Entry Log (Attachment 1):

(1) Name of person entering containment.

(2) Whether or not person holds appropriate MP&L clearance.

(3) Name of person allowing access if applicable.

(4) Area to be accessed.

(5) Entry time.

(c) Inform the Central Alarm Station (CAS) that a Containment entry is about to be made.

Inform personnel of any special security or (d) lle a l t h Physics requirements which must be in effect during the entry.

p6.3.3 Approve entry to containment g)6.3.6 Log time of containment exit in containment /drywell entry log and inform CAS.

.g 6.4.1 May determine that a drywell entry is necessary

p 6.4.3 Request the Chemistry section to obtain a drywell air sample.

,p 6.4.4 Contact Radiation Control Supervisor and notify of:

(a) Intent to make a drywell entry and area or elevation of inspection.

(b) Results of drywell air sample.

(c) Status of reactor.

6.4.6 Obtain from Plant Manager approval for drywell entry.

g 6.4.7 Based on drywell air sample, specify if any special equipment is required.

6.4.8

'hDesignate a " standby" man, to be stationed at 4

entrance and keep in touch with the Control Room and i l

drywell and have readily available any standby equipment which may be required.

'}6.6 Initiate a check of the affected area to assure equipment has not been comprised, and notifiy security immediately if he determines that access i controls have been violated.

1 OPERATIONS S ill FT SUPERINTENDENT's REQUIREMENT 9 - PAGE 5

] REQUIRED ACTION FREQUENCY REFERENCE 4; 7 Releasing 2.3.1 permanent plant equipment and facilities N/A 01-S-07-1, Rev. 4 f' for maintenance. Control of Work on

) 2.3.2 Plant Equipment jI Release of all fire protection, security computer and Facilities and engineer processor equipment, regardless of location, for maintenance work.

l 2.3.3 f Ensuring that equipment returned to service is

! capable of performing its intended function.

i b Review all trouble tickets submitted by GCNS N/A 01-S-07-2, Rev. 1 i

employees in order to remain cognizant of 1 plant status.

i The review includes:

j3 2.1.1 Approve or disapprove t'e trouble ticket

.i depending upon the validity o f the trouble identfied or work requested and assign a number of all approved trouble tickets.

2.2.2 Evaluate the need for initiating any necessary report such as an IR, PQDR, or HW R .

Q 2.2.3 1 Maintain a suitable file to track trouble ticket status for those which reflect problems with plant

} equipme it and facilities.

! {) 6.1.3 Assign each trouble ticket a number to be used i when referencing.

lg 6.2.2 fl (a) Review trouble ticket as submitted by originator. Check for completion and warranty. Sign item #5.

, (b) Approve or disapprove.

l ((c) Assign a number to approved ticket, (1) Maintain a log of assigned numbers i I d) Review the significance of the ticket and

{j (i n i t i a t e :

d)4 (1) An IR and/or Reportable Occurance I Report.

(2) a PQDR (3) a MNCR (e) Classify as safety or non-safety related Ensure necessary work priority.

( f) Return disapproved tickets to originator.

Send copy to Plant Quality Superintendent.

Distribute approved trouble tickets.

(1) Keep one copy (green)

(2) Send original and others to Plant Quality Superintendent

l

, OPERATIONS Sil I F T SUPERINTENDENT's REQUIREMENTS - PAGE 6 REQUIRED ACTION FREQUENCY REFERENCE

- (g) All trouble tickets will be delivered to Plant 1/ day 01-S-07-2, Rev. 3 Quality by the night shift superintendent at the Trouble Ticket end of his shift.

l (1) If considered high priority, hand carry to Plant Quality for immediate processing (2) Maintain a suitable deficiency tracking file using the trouble ticket copies and/or the

[

l associated MWO copies such that any documented j plant equipment or facility deficiency can be {

tracked until completed. {

l 2.1 Responsible for all releases during his shift. N/A 01-S-08-ll, Rev.0 l 2.5.1 N/A 01-S-08-12, Rev.1 Provide signature authority for batch release of waste fluids from Grand Gulf site.

2.5.2 May, based on chemical parameters of emergency -

needs, allow the transfer of fluids from holding tanks to settling ponds. Any emergency transfers will require completion of the Batch Release -

Control Sheet with comments explaining the nature of the emergency.

g 6.1.5 _

r Review the analysis results, emergency requirements, recommendations, and approve a disposal method.

c) 6.7.2 I Notify the Environmental Monitoring Coordinator immediately upon being advised of an out of limit release.

p 2.2.1 N/A 01-S-08-14, Rev.D Document there is a spill and coordinate cleanup efforts.

2.2.2 Responsible for immediately notifying the

Environmental Monitoring Coordinator. ~ ^

2.2.3 ~

Notify the Maintenance Superintendent and/or '

Construction Superintendent for personnel to '

contain and cleanup the spill.

s m

p 2.2.1 Document spill and coordinate the cleanup efforts. N/A 01-S-08'15, Rev.0, 2.2.2 Responsible for notification of the Environmental s ' ~

Monitoring Coordinator, m

{)2.2.3 Notify the Maintenance Superintendent and/or Construction Superintendent for personnel to ,

contain the spill and subsequent cleanup. -

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OPERATIONS S ilI FT . SUPERINTENDENT's REQUIREMENTS - PAGE 7

' N REQU Ihn:D ACTION .

~

FREQUENCY

^

REFERENCE T ,Y f- ., V_

hf)csignated as Sh if t F i r e ' C h' i e f . Re[ponsible for: N/A 01-S-10-1, Rev. I g2'.3.1 s

~-

-Knowing physical' layout o fs plant and (quipment Location c+ M p o te n t La 1. fire hazard, working

' knowledge of'alixp1 Ant fire protect'icn' equipment. '

p 7.3.2 ~ . .

E n s u r i n g' . f ij r. prptection.faquipmedt _is checked dduring normal i n s p e c t'i o n's $ n d tours. Initiating 111 appropri?te,correcrive:actiots whenever _

deficienei.es are not3d. s g 2.3.3 Directing the Shift FJr,e' brigade fro ~ "he Control

, Room during-drills and actual e m e r r' 5.3.3 ,

• N/A 01-S-10-2, Rev. O J Th e senior management representatige in, charge of

o ve r a l,1 plant operatipn during each' shifts _

p 6.5.2 (b) is r e r. p o n n i. b i e for d e t e rrain ing whe the r to officially declare an emergency upon notification of a potential emergencyj.nudition, and'thereby activate. the emergency _ plan and originate. If a s p e c i f. i c level is reached, he is immediately responsible for declaring an emergency of"the appropriate class. Declare an unusual event i' there is any _ question in his mind wh' ether a potential emrengec.y candition exist, .

s (a) Take action to enaure the safe action of the-plant.

'(b) Classify the e ra e r g e n c y and notify officials. -

( c-) ; Dispatch, radiological monitoring teams if there is any p o t e n t i a l' ' f o r. r a t i o l o g i c a l 'r'e l e a s e s .

(d)f Anyother emergency actions ' as approprinte.

(3) lL situation requires implemen t: a t ion o f the Emergency P. l a n , he will' assume role'of the Emergency

~

Director.

(c)

Emergeng,v Flan is activated with the '

declaratio'n of en'edergency. ,Continne-a's Emergency Director'until rblihved. ~

(d) Plant- Madager will'49ume role Director-upon striva,1 at C o n t r o ', Room- ' o f Emergency-

~

p 6.2.1 lia i (d) s author.ity to'stop any work thn.is '

'N/A 01-S-ll-Temp 8 interfering with. operation. Includes n unher ' o.f

, person'nel in Control Room and requiring them to' .-

leave. ._ ._

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OPERATIONS SHIFT SUPERINTENDENT's REQUIRESENTS - PAGE 8

,ltEQUIRED ACTION FREQUENCY REFERENCE 1 6.1.5 J

• [(b) Can write authortzation for doctor p r e s c r i bed drugs only.

N/A 01-S-Il-5 6 N/A 02-S-01-2, Rev. O f(a.11.2 ) May authorize copy to be used and has verified duplicated document is current (valve checksheet, system status file).

(b) Place date, time and initial on first page of duplicate document.

(c) Must re-verify every twenty-four hours as a 1/24 hrs current document.

(d) Controls a stamp with place for authorizing initials, date, and time will be used in proving

! duplicate has been verified or re-verified.

(c) Can direct to destroy 2r retain copies.

9 2.2 lI Senior on shift management representative and as N/A 02-1-01-3, Rev. 0 such has uirec; responsibility for the, safe, proper i

and effective operation of the station. Responsible i for ensuring station operations on his shift are conducted in accordance with the Operating License.

Responsible to the Operations Superintendent for all activities, f5.1 Seaior management representative on shift and dir net s the activitica of the Shift Supervisor.

Iloids a SRO 1icense.

p 6.2.1 Directly responsible for safe, proper, and effective operation of the station.

(a) Providing initial approval of all maintenance wgrk by indicating, using his initials on MWO.

1 (5) Approving fire impairments and making the

< required notification to insurance company and fire and safety ecordinator, c) Maintaining the communications interface on shift, between'the Operations Section and other istation sections.

Estabitshing initial communications with D o(d) utside agencies, (CTO, Security, State and i Federal).

(e) Conducting pre-shift briefings.

I ( f) Reviewing test procedures for conflicts, if run correctly.

g) P r ov id i n g individual unit Shift Supervisor the j list of testing and maintenance activities approved, I with priorities.

(h) Assuring that maintenance activities do not interfereiwith each other, testing activities or plant operation.

i 1

Attachment 6A AECM-82/12 PLANT OPERATIONS MANUAL Ds (g\

Volu:ne 2 02-S-01-4 Section 1 ,

Revision: 2 7y Date: 12-11-81 OPERATIONS SECTIO?{ PROCEDURE SHIFT RELIEF AND ICRNOVER SAFETY RELATED ,

Prepared: <1_ _ ,., ,x [, ,, 7 , ,,,,,

[} Reviewed ( (N, . [

Plant Liw Superint,ande ,

PSRC: / ,, .f _

d, -sw /.2 /?lG/ -

Approved: .h , I -

' Opera t.i.ons. " .perintendent Concurrence: '

/N

~ Assistant Plant Manager <

List of Ef fective Pages:

Page: Revision:

1, 2, 4, 5, 6 1 3 2

~

,- ~ Attachment i L ul Attachment II 1

. l l

GRAND GULF NUCLEAR STATION OPERATIONS SECTION PROCEDURE l

Title:

Sh ift Relief and Turnover l No.- 02-S-01-4 1R4 vision: 1 l ! age: 1 l l l l l l 1.0 PURPOSE This procedure specifies the methods used to tran's fer information, responsibility and authority from one shif t individual to another to assure A1 continuity of Operations.

2.0 RESPONSIBILITY 2.1 Operations Superintendent is res pons ib le for all plant operations activities including supervision of the Operations Section. He will make 1s a t;;taent s of operations personnel to a shift (or crew) consistent with the exi3 ting plant requir3ments. H2 will additionally coordinate with other Jection heads far required personnel as signment s .

2.2 Shift Superintendent is responsible for the safe, efficient and proper operation of CCNS Unit I and II including supervision of Operations personnel assigned to his shift. He will additionally implement company policies on shift and Jerve as the Shif t Fire Chief.

2.3 Shift Supervisor is responsible to the Shif t Superintendent for the safe ind efficient operation of his 1ssigned Jnit, including supervison of Operations personrel as signad to his shift and assure that all required posttiani tre fi l le d . He will adviae operators on his shtft in advance

_ of shift positions they are scheduled to fill and as sure that all

()s Operators conduct tne Shift Relief and Turaovec in accordance with this procedure.

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2.4 All Operations personnel assigned to a shift (or crew) will be aware of the position they are to fill on a given day .and promptly report to that designated shift relief location.

3.0 REFERENCES

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3.1 Plant Administrative Procedure 01-S-06 Conduct of Operations .

3.2 Operations Section Procedure 02-1-01 Responsibilities and Authorities of Operations Shift Personnel.

3.3 Operations Section Procedure 02-S-01 Shif t Logs and Records.

3.4 Operations Section Procedure 02-S-01 Station Operation Orders.

3.5 NUREG 0737 4.0 ATTACHMENTS 4.1 Attachment I - Status Checksheet im v

1

4 CRAND CULF NUCLEAR STATION OPERATIONS SECTION PROCEDURh.

l

Title:

Shif t Relief and Turnover l No.: 02-S-01-4 l Revision: 1 l Page: 2 I I I I I .

I i O O  !

j 4.2 Attachment II - Plant Status Report .

1

!, 5.0 DEFINITIONS

• i g 5.1 Area of responsibility - Designated Shif t Positions / assignment identified j in Reference 3.2.

1 5.2 Required positions - A shift position / assignment required to meet the minimum shift complement specified in Reference 3.1.

j 5.3 Log and surveillance sheets are the hard copy records of shif t operations described in Reference 3.3.

I4 6,. 0 DETAILS

• i 6.1 i

Cer.e ral I .

! 6.1.1 All Operations personnel will relieve in their area of

) responsibility.

i, 6.1.2 Current plant (or area) status will be exchanged between the off

] going and on-coming operators. The on-coming operator (s) will i

g tour his area to confirm plant (or area) status and receive an

I area Turnover Sheet in Reference 3.3.

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! 6.1.3 Operations personnel will document that they understand Current plant conditions and assume responsibility for the watch (in their area as appropriate) ~by signing a log (or surveillance sheet) to

that effect.

6.1.4 Non-Control Room personnel should call the Control Room within 15 minutes af ter assuming the watch to notify the Shif t Supervisor j that the Shif t Relief and Turnover has been ef fected in their f area and relay any pertinent status reports to the Control Room. *}

i 6.1.5 In the event a required shift position (as required by Technical S pecificat ions ) is (or will be) vacant the Shif t Supervisor may authorize the continuance of operating activities with one or more 4 positions unfilled for up to two (2) hours while personnel are being called with the concurrence of the Shif t Superintendent.

i'

a. The Shif t Supervisor shall log the fact that the shift is running chort and indicate the personnel have been j contacted to report to work.

b. If a required position must be filled with personnel on overtime, it shall be scheduled in accordanca with section i

6.3 O '

. - - - - - - , - , - - _ . - - ~ -, - - - . _ - , . - . -. . - . . . - - - - - - . - . - -- -. .- - - , -

GRAND GULF NUCLEAR STATION OPERATIONS SECTION PROCEDURE l

Title:

Shift Relief and Turnover l No.: 02-S-01-4 l Revision: 2 l Page: 3 l l 1 I I I

% c. If a required position cannot be filled within the two (2) hours, the Shift Supervisor shall direct the Control Room operator to place the af fected unit in an operating condition consistent with the existing shift complement .

r is 6.1.6 Any licensed operator assigned to the on-duty shif t may relieve the operator at the controls for a short interval (up to 30 minutes) to allow them to attend to personal needs without c ompleting the entire "Shif t Relief and Turnover" specified in fection 6.2. A simple verbal exchange of current plant status

,ith an entry in the Control Room Operators Log noting the i mpar iry reli e f i.s all that it requir 31 pr 3vi ding the relief i;

.ith the concurrence of -he Shift Surervt;or.

6.l.7 The Shift Supervisor nay be relieved for short period of time as allowed in Reference 3.1.

6.2 Rolief and Turnaver a f Th e 'J i t c h 6.2.1 Th e 2n-camina shif t surerintendent should report 1/2 hr. pri]r to tne normal shift relief. :e shall re new the 3hift 3uperintendcat

.ac Back back to his last ac tive watch , and sizn the log under the last entry. Pri3r to relief af the w it ch he shall restaw the

eneral status af both unit's centrol beard; and rece t le

(_)s  : 3nfirmation from the 3hift Superviuor(s) o f proper canfiguration of controls and systems. He shall review and sign the 3tatus Check Sheet (Attachment I) for each unit. He shall document that ~

he understands current conditions of both units and as sume responsibli.y for tne watch by signing the log to that effect.

1. The Shi f t Superintendent's Shift Relief and Turnover will be conducted in the Shif t Superintendent 's of fice.

6.2.2 The on-coming Shift Supervisor should report 1/2 hour prior to the normal shift relief. He shall review the Shift Supervisor's Log Book back to his last ac tive watch and si gn the log under the last entry. He shall review other logs and records in accordance with Reference 3.3. He will conduct a shift briefing with the on-coming shift to discuss current status of the unit, work plans, and problem areas and operator assignments. Prior to relieving the watch the Shift Supervisor shall review the general status of the Control Room and receive confirmation from the Control Room operators of proper configuration of controls and systems. He shall review and sign the Status Checksheet (Attachment I) and Plant Status Report (attachment II). The on-coming Shift Supervisor shall document that he understands current plant conditions and assumes responsibility of the watch by signing the

! log (or surveillance sheet) to that ef fect .

l g"%-

i w

1

GRAND GULF NUCLEAR STATION OPERATIONS SECTION PROCEDURE l

Title:

Shift Relief and Turnover l No.: 02-S-01-4 l Revision: 1 l Page: 4 l l l l I 1 0 - 0, NOTE In the event a test is being conducted *during the shift relief cnd in the estimation of the Shif t Supervisor, the safety of the plant s'4 may be compromised if the test is stopped to relieve the operator conducting the test, he may choose to keep that operatoc until the completion of the test, consistent with section 6.3

a. The Shift Supervisor will conduct the Shif t Relief and Turnover in the Control Room.

6.2.3 Prior to relieving the Control Room operator on duty subsequent to initial fuel loads the on-coming Control Room operator shall perform a visual check of all critical plant parameters, the availability and proper alignment of all the E.C.C.S. system in the Control Room and a general status of the control boards. He shall fill out, sign and forward the Status Check Sheet (Attachment I) and Plant Status Report (attachment II) to the on-coming Shift Supervisor for his review and signature.

6.2.4 The control room operater shall review tna Control Roun tog Book back to his last active watch and sign under the last entry. He shall review 1 9gs and records in accordance with Reference 3.3.

He shall document that he understands current plant condit io ns and

() assumes res pons ib ility for the watch by signing the log or (surveillance sheet) to that effect.

1.

c 6.2.5 The on-coming Roving Operator shall review the Control Room Log Book back to his last active watch and sign under the last entry.

He shall review logs and records in accordance with Reference 3.3.

6.2.6 The Control Room Operator, and Roving Operator shall conduct the <

Shift Relief and Turnover in the Control Room.

6.2.7 The on-coming non-control room operators shall conduct their Shift Relief and Turnover in their area of responsibility, they shall call the Control Room 15 minutes af ter assuming the watch to notify the Shift Supervisor that the Shift Relief and Turnover has been ef fected in their area and relay any pertinent status reports to the Control Room.

a. They shall review their area log books back to the last active watch and sign under the last entry and document they understand their area status and assume responalbility for the watch by signing the log to that effect.

l i

GRAND GULF NUCLEAR STATION OPERATIONS SECTION PROCEDURE l

Title:

Shif t Relief and Turnover l No.: 02-S-01-4 l Revision: 1 l Page: 5 l 1 i i I fIl>l -

b. The Auxiliary Building Operator will conduct the Shif t Relief and Turnover in the Auxiliary Building using the Area Turnover l Sheet in Reference 3.3. I

• 1

c. The Turbine Building Operator will conduct the Shift Relief and Turnover in the Turbine Building using the Area Turnover l

Sheet in Reference 3.3.

d. The Roving Operator (Roving NOA) will conduct the Shift Relief and Turnover in the Control Building using the Area Turnover Sheet in Reference 3.3.

e. During Refueling Operations the Refueling Supervisor and Operator will ncrmally conduct the Shift Relief and Turnover on refueling floor and spent fuel pool area as appropriate.

6.2.3 All personnel will verbally exchange status confirmation as part of the for~al tu rnover.

6.2.1 In the ev2n that 2 plant evolution or testing is taking place needing continuous aurveillance at the time of Shift Relief and Turnover, it shall take place in the area that the evolution or testing is taking place.

C')

(_/ 6.2.10 The Shif t Supervisor's shall forward Attachments I and II to the Shift Superintendent for his review.

6.2.11 The Shif t Superintendent shall forward Attachment I and II to the Operations Superintendent for his review.

6.2.12 The Operations Superintendent will forward Attachments I and II after his review to Records Department to be placed in the Central Documents and Records System. -

6.3 Replacement / Supplement Shift Personnel 6.3.1 Senior Reactor Operators and Reictor Operators NOTE Overtime shall not be routinely scheduled to compensate for an inadequate number of personnel to meet the shift (crew) staffing requirements. In the event that overtime mu:t be used, due to unanticipated or unavoidable circumstances, :;ie following overtime restrictions shall be followed:

a. An individual should not work more than 12 consecutive hours . l l

l p

.N j

GRAND CULF NUCLEAR STATION OPERATIONS SECTION PROCEDURE l

Title:

Shif t Relief and Turnover l No.: 02-S-01-4 l Revision: 1 l Page: 6 l 1 1 I I I N

O  !/.

~

b. If a Reactor Operator is required to work in excess of 8 continuous hours, he shall be periodically relieved of primary duties at the control board, such. that periods of duty at the board do not exceed approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at a time.

1. 'I c. There should be at least a 12-hour break between all work periods.

d. An individual should not work more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period,

e. An individual should not work acre than 14 consecutive days without having 2 consecutive days off.

f. If an operator is required to work in excess of 12 continuous hours, his duties should be carefully selected. It is preferable that he not be as signed any task that af fects core react,ivity or could aossible endanger the safe operation of the plant.

g. If a Reactor Operator or Senior Reactor Operator has been working more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during periods of extended shutdown (e.g., at duties away from the control board), such individual i

shall not be as signed shif t duty in the Control Room without

()

~

at least a 12-hour break preceding such an assignment.

h. In the event that special circumstances arise that require deviation from the above res trictions , such deviation may be "

authorizeu by the Plant Manager or higher levels of management with appropriate documentation of the cause.

6.3.2 Noa Licensed Operators

a. Overtime for non-license'd personnel will follow normal company '

. policy. Call list and overtime schedules will be addressed in reference 3.4.

(:) '

e

.C R AIID CULP ITUCLEAR STATION CPERATIONS SECTION PROCEDURE O2-5-01-4 Revision 1 B8.08 Attachment I Page 1 of 6 STATt'S GECK 5HEET thi t No. Date Time Pecctor Modre Power MWT MWE . Water ~. ave l Racirculatien Flow Reactor Pressure Feedwater Flow

1. bmGR MCPR MCR . Suppression Pool Temp (Limit Tech Spec 3.2.1) ( Limir. Te ch S pe c 3.2 . 3) (Limit 13.4 rri/FT) (Limit 950F)

Suppression Pool Level Ctmt/ Aux Bldg D/P Cyrvell Press .

(Litit la ft. 5 in.) (Limit -2 to O psid) (Limit 1.75 psig)

Cpper C:ntai:nent Pool Level Upper C:n tain: en: P:o1 Terp

( Li. .it 23 ft. 3 in.) (Limi: 125 %)

a

., o . _ ... m .._w-Safet_rnelirf valves Cperaticnal / / 'CCS / /.

L.C.O.: Tech Spe c 3/4.4.2 App li:2;ili:y: 0: era icnal C:nditi:ns 1,.2,.2nd 3

• cCs i.. ::e ra .i:nal ::ndi icn - Ti 2 all:.ed incpers _ive per Tech spec 01ys IIcurs C=ula .ve inc:e ram ie time Oays Hours Pa car.is :

6 V

A.D.3. Cperati:nal / / 'OCS / / _

L.C.0. Tech 3pec 3/4.5.1 App li: ability : Cperati:nal Ccnditiens 1, 2 , and 3 _

• CCS in operational ccnditien - Time alicwed incperative per Tech Spec Oays Hours C=ula tive incperable time Days _

Heurs Re= arks : i

t.3. ' .v. *a ak ace Cen trol svstam Cperatienal / / 'CCS / /

L.C.O.: Tech Spec 3.6.1.4 Applicability : Cperational Ccaditiens 1, 2, and 3

<CCS in cperational ccnditien - Time alicwed inoperative per Tech Spec cays Hours Cumulative inoperable time Days Heurs P.enark s :

/

w ei-

v - .

S

',. .0 GULF NUCLEAR STATION OPERATIONS SECTION PROCEDURE F .

l 02-S-01-4 i Revision 1 1 89.0S . l Attacament L l Page 2 of 6 l 2 -..-m,,.a -.-:- n..a-- . -- .

Unit No. Cate Tire a a S.3.L.C. Operaticnal / / .CCS / /

L.C.O : Tech Spec 3/4.1.5 Applicabilit/ : Cperatienal Ccnditiens 1, 2, and 5

• tCG in cperatial ecnditicn - Time allcwed incperative per Tech spec Oays 'Hcurs C.= ala tive inoperable time _C av. s ~Mcurs

?a=1rks :

L.? .C.3. 2003 Division I C;eraticnal / / 'CCS / /

L.C.C.- Tech Spec 3/4.5.1 App li cabilief : Cperaticnal Ocnditicas 1, 2, and 3

'CCS in cperaticnal cenditica - Time allcwed inoperative per Tecn Spec Cays He'ars (Nfaiative yj incperab'e : ire

. Cays Mcurs

~ ?.e=arka : --

L.P .C. I . ECC3 Divisien ; FS.R subsys ten "A Cperaticnal / / "CCS / /

L.C.O.: Tech spec 3/4.5.1 Applicability : Cperational Canditions 1, 2, and 3 -

(CCS in cperational cendition - Ti=e allcwed incperative per Tech Spec Days Hours Cumulative inoperable time Cays Hours .

Rmarks : .

L.P . C.I . ECCS Division .II R.9R Subsystem "3" and "C" Cperational /. / *CCS / /

L.C.O.: Tech Spec 3/4.5.1 i App licability : Cperaticnai Ccnditicas 1, 2, and 3 1

'CCS in cperaticnal cenditica - Time allowed incperable per Tech spec Cays Mcurs Re= ark 2 : __ _ _ . . _ . ._ _ w. --

[

• t bJ

.. . ..ww .na s ana wa C '=.

Jc.L L LUN YKULt.U U X.E

.J..*n.

R;visioni 1- 02-s-oi i. i Prgo 3 of 6 l

l- Attschrc.:c I I l 38,08 -

T STAT"S OECGHII'"

Cnit No. Date Time HP . C . S . ECCS Divisien III Cperaticnal / / *CCS / /

L.C.O.: Tech Spec 3/4.5.1 App licability : Cperational Ccnditiens 1, 2, and 3

• CCS in operational conditicn - Time allcsed incperative per Tech Spec Cays Hours Cu=ulative incperable t i .e Cays Mcurs Zamarks:

Centain ent Sorw Cperaticna'. / / 'CCS / /

.C.O. Te ch S:e c 3.5. 3. 2 ~

.t = p li :2b i ' i t f - Operational Ccnditi:ns ' . , 2, and 3

• CCS in cperati:nal cendi:lan - Time alicwed inperative per Tech Spec Cay: Scurs

^=ulat:.: L..0 erab ic time

- C av. s Mcurs (M

./ 7, : arks :

.%.)

Surpressica ?ccl colinc' Cperati:nal / / 'CCS / /

L.C.O. To ca Spec 3.6. 3. 3 -

App licability : Cperational Ccaditiens 1, 2, and 3

• CCS in operational condition - Time allcwed incperable per Tech Scee Days Hours C.=1ulative inoperable time Days Mcurs Rc= arks :

Suppression Pool :takeup Cpertaicnal / / *CCS / /

L.C.O.: Tech Spec 3.6.3.4 Applicability : Cperational Ccnditions 1, 2 , an d 3

• CCS in operational conditica - Tire alicwed incperative per Tech Spec Days Hours Cu=ulative inepe rac le time _

Days Mcurs

, -::': n -.

^

l Y

1

,w ~

l l e l

l

\

l

.- C*w'LF NUCLEAR STATION OPERATICUS SECTIC3 t'Kutt UU ME 02-5-01-4 l R'; vision 1 l At t ach::nnt 1 l Pega 4 of 6 l 38.08' a es c. .

' J .e s psey,c.a. O. .J % CfL e.se Unit No. Date Time

,4.C.I.C. Cperaticnal / / *CCS'/ /

L.C.O. : Tech Spec 3/4.7.4 Applicability : Cperational Conditions 1, 2, and 3 win the Reactor Steam P.kme Pressure '

greater d an 150 psig.

'CCS in Operational cenditicn - Time alicwed inoperable per Tech spec Cays Scurs Cu=ula_ite incpera=le :1 e Oays Scurs Re mar.':3:

1.3.W. Oc.3:a icnal / / 'CC3 / /

L.C.3.- Te:n 3=ec 3/ 4. ' .1 App li cac ility Oper2;i:na1 Candit;cns 1, 2, and 3

• CCS in :cerati:nal condi ica - Time 111 wed inoperable ,:er Tech 3pec 0a73- Hour 3 rm ulative incperacla time Days Mcurs

%):a rk.3 :

A.C. Scurces - C eratin: Cperati nal / / 'CCS / /

L.C.O.- Tech Spec 3/4.3.1 Applicaci.lity : Cperatienal Conditions 1, 2, and 3 .

• CCS in operational conditica - Time allcwed incperative per Tech Spec Cays Hours 1

c.:=ulative incperable time Cays Hours l Remark 3:

l A.C. Scurces - Shutdown Cperati.cnal / / *CCS / /

L.C.O.: Tech Spe c 3. 8.1.2 App licability : Cperational Conditiens 4, S, and when handling irradiated fuel er a spent fue l shic. cin

. n cas t in the seccndary contain=ent.

• ( 0.9 in cperational :cndi 1:n - T ce alicsed incpera:ive per Tech Spec 03Ys Mcurs

,N ula:17e 'nagerac.e_ ice .

. J ay s Mcurs i

I l .

' r< J ea r G :

. D GULF NUCI. EAR STATION CPERATIONS SECTION PRCCEDURE

~

l 02-S-01-4 i Revision 1 l l Attachment I l Page 5 of 6 l ic l

-d 98.08 S . a- r.-.-

a c..,.1.-n_.e v .a. . _ .

thit No . Cate Time 2 D A.C. Cnsite Pcwer Distributien - Oceratine Operatienal / / *CCS / /

Division I, II, and III L.C.O.: Tech Spec 3/4.3.2 App licabili ty : Cperaticnal Ocnditicas 1, 2, and 3 e,.ca e i. , . ~e..1.., . ...,,. , . ~2 2 ..w

. . < n .n. . e a ., ,. W ,s.

.;..C y a. ,2 - ....

.uw - a~-

r w -.,ya .a.- n - ,-.

a Cu=ulative incperamic ti e Cays Mcurs Ps= arks: *

~~~

A. C Cnsite ?cwer riserthutien - S h ':t dm. Cperati:nal / / 'CCS / /

. ., . s. a -.

.,a u.F.C.

- * = ~ - *. a .c a. 3.3..'..'

r

, App licamil;.:y : Ope rati:nal 2:ndi _icn3 ;, 5 1.d when handi .ng irr a diata fue'. cr a 3 pan:

('

v.j) fuel shipping cas t in he seccndarf centai . ent.

• CCS in cperati:nal acndition - Time allcwed inceerative c.er Tec Spec . Cays Mcurs C:mulative incpe rable tire Cays Heurs Pararks:

• C D. C. Dis trib ution - Cce rating Cperaticnal / / *CCS / /- .

Civision I, II, and III '

L.C.O.: Tech Spec 3.8.2.3 Applicability : Cperatienal Cenditiens 1, 2, and 3

• OCS in operaticnal cond..tien - Time allcwed inoperative per Tech Spec Cays Hours Cu=ulative inoperable tire Days Hours Pmmarks :

D. C. Distributien - 3h ur dcwn Opera tional '

/ 'CCS / /

[' " K 8 (j.C.C. Tech spec 3.3.2.4 Applicabili y : Cperational COnsitiens 4, 5, and -hen handling irradiated fuel or a spent fuel shipping cast in th e s e ccnda r f cen tain:,e n t .

• CCS in Ope raticnal :end :ica - Ti..u all:we d inepe ra tive pe r T 2 :h Spec Cays licur3 0 =tu la tive inop e r atab le tire 0173 '!Our3

• 4 OULF liUCLEAR STATION OPERATIONS SECTION PROCEDURE

• • R; vision 1 l 02-S-01-4 i l l' \ .

.. l Attachment I i Page 6 of 6 l n.

RT l l 1 hjl 38.08 l STATUS CHECKSREET s2 "ote Note reasons if unit is restricted from fuel power operation.

Remarks:

Date Time

! Control Room Operator's Signature Date :i=e 3..;.; Su;,er...c; 2 5-gaa; ace Date Time Shtic Superintendent's Signature

' GRAND GULF NUCLEAR STATION OPERATIONS SECTION PROCEDURE l l RT l l l 02-S-01-4 i Ravision 1 l l B8.09 l l Attachment II l Page 1 of 4 l 4 PLANT STATUS REPORT I

DATE TINE i

500KV Yard Line Up as Checked Below

[ ] 5212 [ ] 5224 [ ] 5236 [ ] 5248

[ ] 5208 [ ] 5220 [ ] 5232 [ ]

[ ] 5204 [ ] 5216 [ ] 5228 [ ] 5240 St 11 [ ] Enerzized [ l Deenergized St 21 [ } Energized [ l Deener2ized i l Bus llR [ ] Energized [ ] Deenergized 3us 21R [ ] Energized [ ] Deenergized Bus 12R [ ] Energized [ ] Deenergized Bus 22R [ ] Energized [ ] Deener gized ,

Bus 13R [ ] Energized [ ] Deenergized Bus 13R [ ] Energi' zed [ ] Deenergized

! 30? Trans fo rmers llA IIB 14 12A 12B 21A 21B 24 13 23

[ l [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]

Deenergized [ l [ ] [ l [ ] [ ] [ ] [ ] [ ] [ ] [ ]

BOP Buses Energized from

~

llHD 12HE 13AD 14AE 21HD

[ ] 113 (BOPX) { ] 123 (30PX) [ ] IIA (B0PX) { } 11A (BOPX) { ] 21B (BOPX) l [ ] 12B (BOPX) { ] llB (BOPX) { ] 12A (BOPX) { ] 12A (BOPX) { ] 123 (BOPX)

[ ] Deenergized [ ] Deenergized [ ] Deenergized [ ] Deenergized [ ] Deenergized 22HE 23AD 24AE 18AG 28AG

[ ] 12B (BOPX) { ] 12A (BOPK) [ ] 12A (BOPX) { ] BOPX 13 [ ] BOPX 23 i

CROSS CROSS

, [ ] 21B (BOPX) [ ] 21A (BOPX) { ] 21A (BOPX) { ] connected [ ] connected

[ ] Deenergized [ ] Deenergized [ ] Deenergized [ ] Deenergized [ ] Deenergized ESF Transformers i

ESF 11 [ ] Energized [ ] Deenergized ECF 12 [ ] Energired I ' t:4ne gized

) ESF 21 [ ] Energized [ ] Deenergized Remarks:  ;

i

__ . _ _ _ ~ , , , . - ~ , _ . _ , _ , . . _ . _ _ , . _ _ . _ . _ -,

GRAND GULF NUCLEAR STATION OPERATIONS SECTION PROCEDURE l 02-S-01-4 i Ravision 1 l

l Attachment II l Page 2 of 4 l i

!O ESF Distribution BUS ESP 11 ESF 12 ESF 21 DEENERGIZED DIESEL 15AA { } ( ] [ ] *[ ] [ ]

• • O 16AB ( ] [ ] [ ] [ ] [ ]

17AC [ ] [ ] [ ] [ ] [ ]

25AA [ ] [ ] [ ] [ ] [ ]

26AB [ ] [' ] [ ] [ ] [ ]

27AC [ ] [ ] [ ]

[ ] [ j

{

i 1

DC Buses llDA llD3 IIDC llDD llDE llDG 21DG llDH 11DJ Charger M [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]

Charpr '3 [ ] [ ] [ ] [ ] [ ] [ } [ ] [ ] [ }

I Normal ( l [ ] [  ! [ ] [ ] [ ] [ ] [ ] [ ]

i Eaualize [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ]

' O 34ttery axe Closed [ ] [ ] [ ] [ ] [ } [ ] [ ] [ ] [ ]

, Battery Bkr Open [ ] [ ] [ ] [ ] [ ] ( } [ ] [ ] [ ]

llDF [ ] Energized

[ ] Deenergized Uninterruptable AC i 1Y79 1Y80 lY81 1Y82 4 Normal [ ] [ ] [ ] [ ]

Alt. Supply [ ] [ ] [ ] [ ]

Shutdown [ ] { ] [ ] [ ]

Remarks:

I i

( e' O

5

9 I. .

GRAND GULF NUCLEAR STATION OPERATIONS SECTION PROCEDURE

] RT l l l 02-S-01-4 l Ravision 1 l l . B8.09 l l Attachment II l Page 3 of 4 l h Condenser water box' drain and recire. A() B[ ] S/D [ ]

Main. Turbine Control Fluid A( ] B( ) C[ ] S/D ( l L. O. Conditioner [ ] Operating ( ] S/D d'D TBCW A[ ] B[ ] C[ ] S/D [ ]

Heater Drain Pump A ( l B ( ] S/D { ]

Condensate Pump A [ ] B[ ] C( ) S/D [ ]

Condensate Booster Pump A [ ] B[ ] C( l S/D [ ]

Candensate Deminer-slizer in Service A[ ] 3[ ] C[ ] D( l E( ) ?[ ] G( .} H[ ] S/D( l Recire MG A[ ] 3[ ] S/D( }

Main Turbine Aux Oil A[ ] B( } C[ ] S/D( ) -

Shaft Lift Pump ( ] Operating S/D( ]

Precoat Filter A ( ]On Line [ ] Hold [ ]S/D Preccat Filter B [ ]On Line [ ] Hold [ ]S/D Praccat Filter C [ ]On Line [ ] Hold [ ]S/D

() Circulating Water Pumps A[ ] 3[ ] S/DL ]

Service Air A( ) 3[ ] S/9( ]

Instrument Air 1[ ] 2( ) Supplied by Service [ ]

Aux Boilers A [ ] Operating S/B( ] S/D( ]

[ ] Operating S/B( } S/D{ ]

Demin Water A S/B( ] [ ] Auto [ ]Off Demin Water B S/B[ ] [ ] Auto ( ]Off Domestic Water A ( ]On S/B( ) S/D( ]

Domestic Water B [ ]On S/B( ) S/D( ]

CRD A[ ] B( ) S/D( }

CCW A[ ] B( ] C[ ] S/D( } l Plant Chillers A[ ] B( ) C[ ] S/D( }

1aaar42- - +s -

D .

_ _ _ = . _

j . .

GRAND CULF NUCLEAR STATION OPERATIONS SECTION PROCEDURE l RT l l l 02-S-01-4 I Revision 1 l l B8.09 l l Attachment II l Page 4 of 4 l Radial Well Pump A[ ] B[ ] C[ ] D[ ] E[ ] F( ] S/D[ ]

SSW A [ ] Operating ( ]RJcirc [ ] S/D

• D SSW B ( ] Operating [ ]Recirc [ ] S/D SSW C [ ] Operating [ ]Recirc [ ] S/D j SSW Fans A[ ] B( } C[ ] D[ ] S/D( ]

1 Containment Cooling A[ ] 3[ ] C[ ] S/D( ]

i 2

Drywll Coolers IA[ ] 2A[ ] 3A( } 4A[ ] 5A[ ] 6A[ ] S/D( ]

i 13[ ] 2B[ ] 3B( l 4B[ ] 5B[ ] 63[ -] S/D( ]

Fuel Pool Cooling A[ ] 3[ ] S/D( }

, CRWST A[ ] 3[ ] (CST) A[ ] B[ ] (RWST) S/D[ ]

! P.C.W. Pumps Primary [ ]A ( ]B [ ]S/D

AB Sec ( ]A ( lB [ ]S/D

$ T3 Sec ( ]A { ]3 [ ]S/D C0 Sec ( ]A [ ]B ( ]S/D i

O Remarks: ___

i I

4 1

Control Room Operator:

l Shift Supervisor:

_ / 6;? *.- }

.Q,* e 4%ps w w 4-. .,.w. .,-a, ...c.... ......-. . .. . . . . --- . . . . . . ....u.

1V J. . ,i . . .

l- ..

. OPE?ATIONS SECTION DIRECTIVE 'lEVIE'J TPANSMITTAL

/-

/ \ ' '

sD To / s ( ) "- ( 7 d ' l DirehtiveTvne: p y Section Procedure ( ) Revision

( ) Section Instruction ( ) Te:porary Change

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( ) Quality ( ) Fir.al Signatre

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,L...,.,.J c., ....a...,... ( ) Shi#t Surerfisc7, ~j (Cc=enta may be either marked on the directive or entered on the ce=ent sheets.

If the directive is : narked, indicate below and initial /date the directive.)

~

Directive carked-up and attached: yes ( ) no C Co=entrentered on co=ent sheets and attached: yes ( ) no )

/ -fle I YNNt ' jY R diewe'r's Signature 'Da te Coment Resolution: .

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All cer.ents shcun above have been resolved.

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a  ?'r wtrer ana ne.itawer Due

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u.uu.O u u t.: .. t, u ..u a . .s . . ,i6 i01-S-02-2 iRev. 3 1

• ' l Attachment LLI iPaze 1 ot 11 TEP.PORARY CHA'CE N0iICE COVER SHEET i D treet tve No. C2-S-01-5 IC:i ;io. 3 Date 11/?f811 l '

l Title Shift L o r: s and R e r- o r d s  !

I l

s - 1r iLatest Revision 27o. O SAFETY RELATED [gx ]YES ( ]!i0 l 1

REASON FOR CHA :GE: (Describe why the TC( is being issued, and if appropriate, su:narize what procedural chan;;es are involved)

Add new secticn.

IS ST 7'?CT' C:i 3 7:R E ST '.Y : In accordan .3 wi:h Adminis : rat ive ? r c adure 01-S-02-2, wri:2 One ICS Succer in :he lower right portica o f directive's cover sheet, initial, and date. The directive shall be =arked up :o reflect changes sta:ed.

4

(*.!. T *,. *. .* (*. ** .7 *_ n_ 77

~ . 5 4.*s." ..7. . 333 ;77zcggg p;33, e

(~'tg Initial Di; ribution: Operations Shift Superintendent (1)

'w[ Control Rcca (l)

Of fice Seriices Superviaor (1)

PSRC APPROVAL REQUIRED [XX ] YES ( ] N0 lLatti.it Accrovall i

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02-S-01-5, Rev. O, TCN #1

1. Add to Section 6.1.2 (Page 3) : n. , System Status File

2. Add Section 6.15 to Page 20:

s1 6.15 System Status File 6.15.1 Purpose - This file is maintained to provide a readily a cce s s ib le source of infcnnation on the status of all systems to operators. Each system shall have a f older in the file which shall contain, but not be limited to the following:

(1) Valve Lineup Sheet, (2) Copy of pending MWO's, (3) Copy of installed Temporary Alterations, and (41 Copy of pending CWP's.

6.15.2 Responsibility - It shall be the respcasibility of the shift Supervisor to assure this file is properly maintained per procedure 02-3-01-2.

6.15.3 Rules of Maintaining, Review and Retention - The shift Superintendent shall audit this file once per g~3 month and document this audit to the Operations

(_) Assistant during the first working week of ch month n

b l $

1

l Attachrent 7 CG AECM-82/12 FSAR 13.2.4 Fire Brigade Training 4

13.2.4.1 Instruction for Members of the Fire Brigade Prior to assignment to a fire brigade, personnel shall receive instruction in the following topics:

1. Identification of fire hazards (and their location) and associated types of fires that occur in the plant.

1

2. Identification of areas where breathing apparatus is required, regardless of the size of the fire, i

3. Identification and location of installed and portable firefighting equipment in the plant.

4. Familiarization with plant layout including access and egress routes for each area. i

5. Proper use of installed and portable firefighting equipment including the station fire truck.

I

6. Correct methods of fighting various types of fires. This shall include electrical fires, fires in cables and cable trays, hydrogen fires, flammable liquids, vaste/ debris fires, and record file fires.

7. Indoctrination in the Fire Protection Plan and Implementing Instructions. This shall include individual and fire brigade responsibilities. [

8. Proper use of breathing, communication, lighting, portable ventilation equipment, and radiation protection equipment.

9. Detailed review of fire protection plan implementation instruction,  !

! with particular emphasis on equipment to be used in particular areas.

10. Review of modifications, changes, etc., to the physical plant, procedures, firefighting equipment, or Fire Protection Plan.

11. Methods of fighting fires inside buildings and tunnels.

i

12. 'dentification of high radiation areas, potentially contaminated i

areas and methods for fighting fires in regulated areas.

[

i

13. Applicabic first aid methods.

14. The toxic and corrosive characteristics of expected products of combustion.

l.

1 B52phl  !

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-~ . . ._ _-_ _ - _- _ . _ _ _ _ . -

i 1

cc FSAR In addition.to the above topics, fire brigade leaders and the Station Fire

Chief shall receive training in directing and coordinating firefighting activities.

J

. Rcf resher training in the above topics will be conducted annually. The

refresher training will be scheduled by the Training Coordinator for each fire j brigade member. The sessions will be conducted quarterly and will be repeated

, every year.

l j 13.2.4.2 Practice for Fire Brigades I

1 Annually, each fire brigade member shall practice the proper method for extinguishing the various types of fires. Actual fires shall be extinguished except that energized electrical fires may be simulated.

Each fire brigade member shall also practice techniques that raquire the use of protective breathing equipment. These practice sessions may or may not involve actual firefighting and shall be conducted annually.

13.2.4.3 Fire Brigade Drills 1 Fire brigade drills shall be performed to promote effective teamwork on the

} 11re brigade. Various types of drills include, but are not limited to, the I

following:

1. Simulated use of equipment for various situations and types of fires which could reasonably occur in various areas of the plant. The simulations shall stress conformance to proper procedures and established firefighting plans.

2. Actual operation of fire protection equipment where practical. This includes breathing, communication, portable lighting, and ventilation equipment.

! Fire brigade drills will be conducted using the following guidelines:

,' l. Each fire brigade shall be drilled at least per quarter.

2. Each fire brigade member should participate in each drill. Each Fire Brigade member shall participate in two drills per year, as a minimum.

l l

3. One drill per year for each fire brigade shall be unannounced. Each unannounced drill shall be separated by a minimum of four weeks.

4. One drill per year will be conducted on a backshif t for each fire brigade.

5. All drills will be pre-planned to meet established training objectives and shall be critiqued to determine the effectiveness in meeting these objectives.

B52ph2 )

I GG FSAR l 6. Unannounced drills shall be pre-planned and a drill critique held by I

a board of responsible management personnel.

l 7. Performance deficiencies of fire brigades or individual fire brigade

members will be corrected by providing additioning training for noted weak areas.

1

8. An unsatisfactory drill performance by a fire brigade will be corrected by providing additional training for noted weak areas. A l repeat drill will be held within 30 days of the critique, i 9. At least once every three years. a randomly selected unannounced

drill shall be monitored and critiqued by a group of qualified individuals who are independent of the GGNS staff, f 10. Each fire brigade drill shall be evaluated on the following, as a minimum

a. Assessment of fire alarm effectiveness,

b. The time required to notify and assemble the fire brigade.

c. The selection, placement and use of equipment and fire fighting strategies.

d. An assessment of each fire brigade member's knowledge in the j fire fighting strategy and techniques for the fire area.

a

c. An assessment of the brigade's conformance to established plant 1 fire fighting procedures and use of the fire fighting equipment, including self-contained breathing equipment, communication equipment, and ventilation equipment when applicable.

I

f. Assessment of the. fire brigade leader's effectiveness in directing the briMade's activities.

13.2.4.5 Program Administration Instruction in the above topics will be coordinated by the Training and Administrative Superintendent. The instructor assigned will be knowledgeable on the topics and experienced in fighting the types of fires that could occur in the plant. He shall also be qualified to operate the fire protection  ;

, equipment installed in GGNS. Generally, fire brigade leaders will be used for

! this instruction.

The Training and Administrative Superintendent shall be responsible for scheduling, conducting, and documenting the fire brigade drills. He shall prepare drill scenarios for all drills.

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l B52ph3

=_ __ . _ - - _ _. . _ - . _ _ _ _ _ _

l i GG l FSAR 13.2.4.6 Instruction for all Station Employees Each permanent plant employee shall receive an indoctrination on the Fire Protection Plan evacuation routes f rom his normal place of duty, and procedures for reporting fires.

In addition, security personnel shall receive instruction that addresses entry procedures for offsite fire departments, crowd control for persons exiting the station, and procedures for reporting fires during their tours of the statica.

} Temporary personnel should be instructed in evacuation signals, evacuations routes, and fire reporting procedures.

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13.2.4.7 Drills An annual evacuation drill will be conducted.

1

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4 B52ph4

Attachment 8 GG AECM-82 / l'2 -

FSAR Resume No. 74 Name: John I. Paulk Birthdate: 1928 Formal Education and Training:

Vanderbilt University, 1946 - 1948 B. S. Cencral Engineering, U. S. Naval Academy, 1952 Ph. D. Nuclear Engineering, North Carolina State University, 1962 Experience:

1952 - 1956 U. S. Air Force Nuclear Supervisor 1956 - 1957 DuPont Associate Service Engineer 1961 - 1963 Tennessee Valley Authority Reactor Physicist 1963 - Present Mississippi State University 1963-1964 Associate Professor; Nuclear Engineering, Research at Savannah River in 1964 1964-1980 Professor and IIcad of Department of Nuclear Engineering 1981 - Present Associate Dean for Research, Director of Engineering and Industrial Research Station and Professor of Nuclear Engineering Conducted or directed research on hermetic seals, core analysis, diffusion of thermal neutrons, diffusion of fission gases and other nuclear related subjects.

Publications:

The Dif fusion Parameters of IIcavy and Light Water Mixtures at Dif ferent Temperatures by the Pulsed Source Method, Dissertation, North Carolina State University, 1962, and with A. W. Waltner in Transactions of the Ancrican Nuclear Society, November 1962.

Neutron Generator Experiments, Experimental Physics Division Quarterly Report, l Savannah River Laboratory, with P.B. Park and N.P. Baumann, November 1964.

l l llermetic Seal Test Evaluation, Engineering and Industrial Research Station Report, Mississippi State University, with C.R. Iloke and E.F. liarwell, June 1965.

! 13A-174 Clrg86

GG FSAE John I. Paulk - continued _

liercetic Seal Evaluation for Electronic Components Engineering and Industrial Research Station Report, NUE 004, with R.D. Guyton et al., 1908. .  ;

^

Correlations of Measured Leak Rates by ifelium Mass Spectrometer and Radioactive Gas Techniques for Crystal Can Relays. Paper presented during Seal Integrity of Electronic Parts Seminar at Marshall Space -

U

'J Flight Center, with M.J. Berkebile, September l'96S.

Effect of Very Slow Reactions of Elemental Carbon on its Return' to Biological ,

Cycles, Developments in Industrial Microbiology, Vol. 14, 1973, with R.G. -

Tischer and J.S. Dhindsa. '

s K Sterilization of the Boll Weevil by Radioactive Fumigation, Journal of Gegtgia -

Entomological Society. Vol. 13, (4), 1978, with J.W. Ilaynes, J.R. Dawson, and Norman Mitlin.

l A Manual of Nuclear Engineering Experiments, Vol. I and Vol. 2, coauthored . ~

with Dr. P.S. Shich, for use in nuclear engineering laboratnry dourses. N  !

u Professional Memberships:

~

American Nuclear Society 4 s

4 Sigma Pi Sigma . ,.

Sigma Xi Tau Beta Pi .

Atomic Industrial Forum Professional Engineer - Mississippi Chairman, Nuclear Energy Committee, Mississippi State University ' '

Member, Mississippi Radiation Advisory Council s , _ <

I I

1 I

13A-175 i

l Clrg87

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i s , (fg FSARt ,

, , P.esun.c No. j

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_ Name: El,ler,[ N Hammogi s n- '-. ,

~

, y Bi r tit !a te : 1936 "- N s y

( - ,

<r Formo',Educara.du and Training: y  ; ,

. \ '+

BSME Northeastern Universi.ty, 1959 i

EbME Northeastern UnQicr..ity,' 1962  ! ' '

s, Twe years of graduate voi k- in Buainess Admin'istration at Northeastern Ifniversi ty - x j

Ter. medh cource of Univac Compttter Psogrcmming N i Tv;.veck course at BaDey Meye7 Cor pany for tinline cycle work Two week course at M.L f. in 7ater Cooled Reactor Safety Fifteen week course af Yankee for rcuttnr sperator license Received R.O. License #2055 at Yankea un October 26,--1966 Five week BWR Orientation course Oqe week BWR Simulators course at General $lectrics Tiaining Center cot;rae required for Senior Reactor Operator Cold 1.icense nj _Five week BWR Technology course ', '

b) , Twelve ticek BWR Simulator course at General f.lectric's Training l Center s ,

! c) op. Week BWR Obstvatic? ' course at Dresden Nuclear Station

'N ceiveds9RO License J198"/ a.t Du1pb J.rnold Energy Center on 12/20/73 Experience: -

s i 1959 - 1961 - Ray (Scon Corporation

, s N' Mechanical engEn'cer - designed and controlled the asscmbly of several complex automatic machines for use in the manufacturing of 111 con transistors.

,7 1961,- 1962 - Clevite Corporation 3echanicalsengineerintrainingforCleviteCorporation. Worked in production, research, and quality control departments. In each s depe rtment was concerned with reducing the costs in the manufacture ofd{odesandtransistors.

i 1962 - 1965 - New England l'ower Company Technical assistant to the Superintendent of Salen llarbor Generating i Statiot.. - Responsible for plant performance testing and calculations on three 125 MWe coal fired units. These teste were i performed on the turbines, boilers, condensers and several other l plant components. Responsible for planning and following overhauls of the turbine and boilers using the critical path method (CPM).

Responsibic for writing reports to the Edison Electric Institute on the plant performances of these three units.

Clrg94

GG FSAR Ellery L. Hammond - continued 1965 - 1969 - Yankee Atomic Electric Company Plant Reactor Engineer - Responsible for all reactor cnd secondary plant performance calculations, special nuclear material account-ability for the plant site, writing of refueling procedures, and all reactor component inspections. These calculations included the react'or performance during many experimental chemical injection tests for pH control and core reactivity anomalies. When operator training courses were conducted, responsible for teaching reactor theory to prospective reactor operators. Conducted all the photogra-phy work required for maintenance records and reports. Besides several refueling reports, wrote a manual on special nuclear material safeguards for the plant and was involved in the format required by the Atomic Energy Commission.

1969 - 1970 - Public Service Company of New Hampshire Staff Engineer - Responsible for the liason between the Production Department and the Engineering Department during the initial design phases for the Seabrook Nuclear Station. Responsible for ensuring that proper operating and maintenance considerations would be incorporated into the design of the Seabrook Station. In addition to reviewing equipment specifications and drawings. Responsible for writing the initial draft of the technical specifications and the N-45 inservice inspection program for the Seabrook Station. Partici-pated in the initial DRL meetings with the AEC prior to the issuance of the Seabrook construction permit. Prior to the Seabrook Station deferment, organized the training program for the station personnel and to coordinate the plant startup.

After the deferment responsible for the mechanical engineering l review of a 400 MW oil fired cycling station. Added unique features to a standard oil fired unit; induced draft fans to obtain negative boiler pressures and an electrostatic precipitator to remove parti-cules in exhaust gases.

1970 - 1979 - Iowa Electric Light & Power Co.

1970-1971 Nuclear Design Engineer Responsible for assuring that the design of nuclear oriented systems conformed to proper engineering standards required by the AEC. This job entailed the review of piping and instrument drawings, functional control diagrams, equipment specifications, layout drawings and other related design considerations. Provided the information for decisions that concerned the operation of the facility.

These decisions affected plant and administration building layout, shielding layouts, computer programs for plant perform-ance caluclations and various other Production oriented items.

Responsible for conducting a primary containment leak rate test on the bare containment that utilized the " absolute" method of

' calculation during the Chicago Bridge and Iron's acceptance test of the vessel.

C1rg95

r GG FSAR Ellery L. Hammond - continued Responsible for the detailed layouts of the NSSS main control room and radwaste control room panels.

1971-1976 Assistant Chief Engineer (Assistant Plant Superintendent) for the 550 MW nuclear plant at Palo Iowa. Responsible for the overall direction of major aspects of the Duane Arnold Energy Center which includes proper control over the operation of the facility and its maintenance and technical services activities.

Involved in development of the plant organization and selection of 90 member staff. Additional responsibilities included:

Chairman of Operacions Review Committee, tmergency Director of Duane Arnold Preparedness Plan, Security Director of Industrial Security Plan, responsible for Operating Plant Quality Assurance Program, Training Director and Pre-operational and Startup Test Coordinator.

1976-1979 Chief Engineer of the Duane Arnold Energy Center.

Responsible for the entire operation of the facility. Responsi-ble for administering the union contract and following the job bidding procedures, apprenticeship program progressions and overtime agreements. Participated in the management-union negotiations for new contracts. Responsible for hiring policy, budget system, management control system and revised security plan.

1979-1980 Manager of Nuclear Operatiens for the Duane Arnold Energy Center. Reported to the Assistant to the Vice President on matters pertainin( to the operation and maintenance of the Duane Arnold Energy Center.

1980 - Present - Gulf State Utilities Plant Manager of River Bend Nuclear Station. Responsible for developing a plant staff, procedures, training programs that will allow River Bend to meet the NRC requirements prior to fuel load.

Once the facility becomes operational, and will be responsible for the entire operation and maintenance of the plant.

Professional Memberships American Nuclear Society Secretary for the Reactor Operation Division Chairman BWR Owners Group Submittee on Control Room Improvements Member Grand Gulf Safety Review Committee 1

l Clrg96 .

GG FSAR Resume No.

Name: Jackson B. Richard Birthdate: 1930 Formal Educatior and Training:

Undergraduate Studies in Architectural Engineering, Louisiana State University B.S. Science and Engineering, U.S. Naval Academy Chief Reactor Operator Training, U.S. Navy Ballistic Missile Schools, U.S. Navy Prospective Commanding Officer Schools, U.S. Navy Experience:

1952 - 1978 - U.S. Navy Engineering Officer, Executive Officer Commanding Officer, Division Officer, Deputy / Division Director Pentagon and White House Staffs.

Shipboard power plant related management background and achievements incivded successful, safe and reliable " hands-on" operation, main-tenance, and preparation for inspection and certificatioa of one oil-fired steam, two-diesel-electric and three nuclear power plants.

Included was: Construction coordination, oversight, testing, and initial operation of three nuclear power plants; preparing and organizing, plant and ship operating, maintenance and emergency procedures; establishing, operating and supervising equipment and machinety preventative and corrective maintenance programs.

Headquarters positions ashore included a broad range of responsi-bilities in positions with the following offices; Office of the Chief of Naval Operations - Staff Officer and Branch Head in Current Plans and Policy Branch of Strategic Plans, Policy and Operations directorate; Office of Naval Intelligence - Division Director and Intelligence Programs Manager; b"r mi of Naval Personnel - Project Management Of fice Deputy Director and Disision Director in Human Resource Management directorate; Executive Office of the President of the United States - Special Action Office Deputy Assistant Director and Military Aide.

Headquarters management achievements included: Establishing and ,

operating a new federal action office; establishing and operating a

new naval project office for development of innovative concepts of l human resource canagement; establishing and operating a new naval staff division created to develop personnel programs; operating a staff division managing two highly successful technical information collection programs, directing an annual $15 million special. equip-ment procurenent program, and marketing and sponsoring a $1 billion electronics system development and procurement program (FY 1974-75 dollars); budgeting, managing and controlling financial resources, j Additional shipboard related management background and achievements I included instituting programs for and conducting recurring squadron level annual operational reactor safeguards examinations for eight j nuclear power plants. '

h Clrg97

GG FSAR Jackson B. Richard - continued During two years as Commanding Officer of a Naval Submarine Base, achievements included successful management of a complete range of industrial and personnel support services. Included was: operating a marine and power plant intermediate repair activity which accom-plished nuclear reactor, electrical, mechanical, piping, structural and electronic repairs and alterations, including planning, estimat-ing, work force management, quality assurance, and radiological

> controls support; providing annual repair facility labor output of 800 man-years; budgeting and financial control of a $15 million annual operation (FY 1976-77 dollars); providing personnel support services for a staff of 1200 and a tenant population of 3500; security, environmental monitoring and disaster control plans, preparations and services; operating, maintaining and upgrading a

$275 million replacement cost base (FY 1977 dollars).

1978 - 1981 - Nuclear Systems, Inc., Baton Rouge, La.

Vice Presider.t and Secretary-Treasurer, General Manager of Gamma Industries Division. As chief Operations Officer, was responsible for all management, operations and profit / loss aspects of business of Gamma Industries, a manufacturing, sales and service business providing radioisotopes and tiher manufactured products t: the non-destructive testing industry and specialized nuclear and engineer-ing services to the manufacturing and construction industries.

During the period, increased Gamma Industries' sales 63% and improved division financial performance from loss to significant profit.

Achieved Gamma Industries business sales volume of $4.5 million for FY 1981 with 50 employees. Managed extensive Gamma Industries involvement with State and Federal agencies regulating the radio-isotopic and radiography application industry. As member of cor-porate management team, significantly contributed to reversal of Nuclear Systems, Inc. financial performance from significant loss in FY 1979 and FY 1980 to solid profit for all four quarters of FY 1981. As Corporate Secretary and Corporate Treasurer for the first two years, coordinated trata ! tion of all company business to a computer system and assisted in actions to divest a totally owned subsidiary corporation and plan and start up a new operating division.

1981 - Present - Middle South Services, Inc.

Principal Nuclear Engineer and Manager, System Nuclear Operation.

Consultant services include sitting membership on Safety Review Committecs, analyzing ongoing operations and safety performance, supporting construction and licensing preparation and reviews and providing special project support for three commercial nuclear power plants.

1981 - Present - Private Consultant, Baton Rouge, La.

Consultant services include analyzing business risks and recommending corporate marketing policies associated with computer equipment sales to the commercial nuclear power industry.

l l

C1rg98

GG FSAR Jackson B. Richard - continued Professional Memberships:

American Nuclear Society Atomic Industrial Forum American Society for Non-Destructive Testing Non-Destructive Testing Management Association i

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l C1rg99

GG FSAR Resume No.

Name: Johnny F. Pinto Birthdate: 1943 Formal Education and Training: i l

B.S. Electrical Engineering, University of Houston, 1971 Electronic Technician Class A School Basic Submarine Training Basic Nuclear Power School Nuclear Power Training Unit Speed Variator School, G.E.

Nuclear lastrumentation and Controls Warranty School, G.E.

Installation and Services Engineering Radiation Protection School G.E.

Field Engineering Program Training, C.E.

Experience:

1962 - 1968 U.S. Navy Electronics Technician - Reactor Control and instrument systems, reactor maintenance and repair.

~

1972 - 1975 General Electric Company 7 1972 Test Engineer - Drive Systems Product Dept. Quality Assurance testing of electronic components.

1973 Engineer - Browns's Ferry Nuclear Power Plant, Electrical and Electronics Nuclear Unit. Responsible for drawing control, ,

hardware installation and checkout, equipment procurement, and onsite engineering revisions.

1973-1974 Startup Engineer - Edwin J. Hatch Nuclear Plant.

Responsibic for construction testing, system verification and preoperational testing of NSSS and BOP. Coordinated activities of 11 man group.

1974 - 1975 Engineer - Brunswick Nuclear Power Station - Originally assigned to coordinate United Engineers and Constructors, Carolina Power and Light and General Electric efforts in -

support of radiation waste preoperative testing to meet end-of-the-year licensing connitment. Efforts resulted in assignment of one year to continue in radiation waste areas and to begin construction testing on second unit in the following areas: 7 reactor re-circulation system, feedwater control, standby liquid contrci, fuel pool cooling and reactor water clean-up.

1976 - 1981 Brown & Root, Inc.

Senior Project Engineer - South Texas Project. Discipline Project Engineer for instrumentation and controls. Participated as a member

• l of the Engineering Project Management team in the overall coordina- ,

j tion of all disciplines. Directly supervised the following disci-i plines in all activities relating to the project: Design Assurance  !

l Group, Nuclear Shielding, Nuclear Analysis, Special Problems, and '

TMI.

C1rg90  !

i GG FSAR Johnny F. Pinto - ccatinued 1981 - Present Mississippi Power and Light Co.

Manager, Nuclear Plant Engineering. Reports directly to the Assistant Vice President - Nuclear Production. Directs the activities of the principal engineers assigned to mechanical, electrical, civil /struc-tural, environmental and operational engineering. Is member of the Corporate Safety Review Committee.

Professional Memberships:

American Society of Professional Engineers Alabama Society of Professional Engineers Institute of Electrical and Electronic Engineers w

t i

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Clrg91 -

GC FSAR Resume No.

Name: Steven P. Hutchins Birthdate: 1952 Formal Education and Training:

B.S. Electrical Engineering, University of Pennsylvania, 1976.

Management Orientation Course, Public Service Electric and Gas Company Experience:

1976 - 1977 Public Service Gas Electric and Cas Company, New Jersey -

Shift Engineer - Synthetic Natural Gas Plant - Provided engineering coverage during plant operation. Maintained functicnal readiness of flow indicators, thermostats, switches, etc. for computer inputs.

Gas Dispatch Computer Engineer - Developed study on how a computer i

could best be utilized for dispatch operations. Drafted CRT display of local mecering stations and all required inputs.

1977 - 1979 Bechtel Power Corporation - San Francisco, CA Field Electrical Engineer - Constructior. Nuclear Power Plant (Susque-hanna Steam Electric Station). Reviewed raceway layout drawings for interferences and design completeness. Performed in-process inspec-tion and field design modifications to seismic raceway and conduit installation, equipment placement, and cable pulling activities.

Determined material and tool requirements by means of drawing take offs System Turnover Engineer - Reviewed station single lines and schema-tic drawings for formation of turnover packages. Developed start-up packages for turnover to the client for such systems as the 125 VDC distribution feeds, the uninterruptible power supplies, and the station computer.

PGCC/ACR Engineer - Coordinated the work activities of 8 engineers for the complete installation, cable pulling / termination, and field testing of a GE supplied Power Generation Control Complex coupled l with an Advanced Control Room. Provided field support to Home Office Engineering for all BOP control room modifications. Coordi-nated backchargeable work activities through GE site engineering for all NSSS modifications and installation of ship-short materials.

Performed in-process inspection for the installation of a transient monitoring recorder.

1979 - 1981 Baldwin Associates, Clinton, Ill.

gp Lead Area Electrical Engineer - (Control & Diesel Generator Buildings)

- Supervised 5 engineers and technical assistants, providing field engineering for installation of lighting, sound power, P.A., fire protection, and telephone systems. Provided field engineering and l

[

Clrg101

GG FSAR Steven P. Hutchins - continued scheduled inputs for the complete installation of a General Electric supplied " Power Generation Control Complex" (including installation, cable pulling, terminations, ship short installation, and design modifications and rework.) Provided field engineering and design input for the installation of seismic class lE cable pan, and conduit supports.

1981 - Present Mississippi Power & Light Co. , Jackson, Miss.

Principal Engineer Electrical Group - Reports to Manager, Nuclear Plant Engineering. Supervises lead and other Electrical Engineers.

Responsible for electrical designs / design modification, electrical cable and equipment layout, electronic engineering and control /

control logic engincaring. Provides consultation advise in all areas of electrical and electronic engineering.

Professional Memberships:

Power Society, Institute of Electrical and Electronic Engineers i

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l C1rg102 4

GG FSAR Resume No. 25 Name: Robert Charles Fron Birthdate: 1954 Formal Education and Training:

l d

B.S. Civil Engineering, Pennsylvania State University, 1976 M.S. Civil Engineering, Pennsylvania State University, 1978 Experience:

, 1976 Pennsylvania Power & Light Company, Berwick, Pennsylvania j Student Engineer - Member of Cost and Scheduling Group for Pennsylvania Power & Light Company at the Susquehanna Steam Electric Station.

1977 Philadelphia E.ectric Company, Pottstcwn, Pennsylvania Student Engineer - Assigned to the Construction Quality Group at the

Limerick Generating Station Construction Project. Duties included review of the technical specifications and the quality control procedures and the monitoring of construction activities.

I 1978 - 1980 Bechtel Power Corporation, Port Gibson, Mississippi Field Engineer - Assigned to the Grand Gulf Nuclear Project as a Quality Engineer and as an Electrical Field Engineer on Unit 2.

i 1980 - Present Mississ ippi Power & Light Company, Jackson, Mississippi 1980-1981 Principal Civil Engineer (Acting) - Assigned to the i

Civil / Structural / Environmental Sub-group of Nuclear Plant Engineering at the Grand Gulf Nuclear Station. Assignments included general civil, structural, and concrete design on several NPE design projects.

i 1981 Manager of Nuclear Plant Engineering (Acting) - During assign-ment at Grand Gulf Nuclear Station developed NPE administrative procedures to respond to MP&L QA and ANSI N45.2 requirements.

I 1980-1981 Principal Civil Engineer - Assigned to the Civil /Struc-tural/ Environmental Sub-group of Nuclear Plant Engineering at the Grand Gulf Nuclear Station. Assignments include general civil, structural, and concrete design on NPE design projects.

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Cirg103

4 I GG FSAR 1 Resume No.

l Name: Milton Lofton Jones Birthdate:

4 Formal Education and Training B.S., Mathemetics Mississippi College, 1971 M.S., Mathematics University of Mississippi, 1976 Experience:

1973 - 1974 Rankin County Schools Mathematics teacher 1976 - 1981 Westinghouse Electric Corp. Lighting Business Unit -

Vicksburg, Miss.

Sales Negotiator, Marketing Representative and Utility Marketing Representative in Marketing Department - four years One year in Engineering Department as Design Engineer in the "Stan-dardization Task Force" analyzing / restructuring all product lines and product information systems including computerized inventory file listings. Collateral duty as the Business Unit Standards Engineer responsible for material / process specifications.

1 1981 - Present Mississippi Power & Light Co., Jackson, Miss.

Engineering Services Supervisor - Nuclear Plant Engineering Reports to Manager, Nuclear Plant Engineering. Responsible for document control, personnel administration, supplies management. Responsible for control and management of the Nuclear Plant Engineering Adminis-tration Manual.

Professional Memberships American Mathematics Society i

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