ML20091C614

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Proposed Tech Specs Revising Various Administrative Controls to Reflect Changes in Offsite Organization Chart (Figure 6.2.1-1)
ML20091C614
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 05/24/1984
From:
MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20091C551 List:
References
NUDOCS 8405300616
Download: ML20091C614 (12)
v • d • e


Text

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l 6.0 ADMINISTRATIVE CONTROLS

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6.1 RESPONSIBILITY GGNS Gene ro l .

6.1.1 The Ment Manager shall be responsible for overall unit operation and l shall del,egate in writing the succession to this responsibility during his absence.

. 6.1.2 The Shift Superintendent or, during his absence from the Control Room, a designated individual shall be responsible for the Control Room command =

function. A management directive to this effect, signed by the Senior Vice President, Nuclear shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support i-shall be as shown on Figure 6.2.1-1.

UNIT STAFF 6.2.2 The unit organization shall be as shown on Figure 6.2.2-1 and:

a. Ea n on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1.
b. At least one _ licensed Reactor Operator shall be in the control roca when fuel is in the reactor. In addition, while the reactor is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Reactor Operator shall be in the Control Room.
c. A health physics technician" shall be onsite when fuel is in the reactor.
d. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities

! during this operation.

e. A site Fire Brigade of at least 5 members shall be maintained onsite -

at all times". The Fire Brigade shall not include the Shift

' Superintendent, the STA, the two other members of the minimum shift crew necessary for safe shutdown of the unit, and any personnel required for other essential functions during a fire emergency. At least one A0 shall be available to respond to non-fire fighting commands from the control room. ,

"The health physics technician and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.

e405300616 840524 PDR ADOCK 05000416 P PDR GRAND GULF-UNIT 1 6-1

i ADMINISTRATIVE CONTROLS UNIT STAFF (Continued)

f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, health physictsts, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. However, in the event that unforeseen problems require substantial amounts of overtime to be used, the folicwing guidelines shall be followed:

1. An individual should not be permitted to work more than 16 huurs straight, excluding shift turnover time.
2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.
3. A break of at least eight hours 'should be allowed between work periods, including shift turnover time.
4. Except during extended shutdown periods, the use of overtime I

should be considered on an individual basis and not for the entire staff on a shift.

GM5 Generd Any deviation from the above guidelines shall be authorized by the

, "unt parkt;nd:nt r hh d:puty, or higher levels of management, l in accordance with established procedures and with documentation of l

l M Q* V the basis for granting the deviation. Controls shall be included in thethe by procedures such that rindividual Fient L,pecintendent overtime his designee shall to assure beexcessive that reviewed month hours have not been assigned. Routine deviation from the above guidelines is not authorized. gg gg g

  • 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.

COMPOSITION 6.2.3.2 The ISEG shall be composed of a multi-disciplined dedicated, onsite, group with a minimum assigned complement of five engineers or appropriate l specialists. I GRAND GULF-UNIT 1 6-2 ,

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GRAND GULF-UNIT 1 6-4 .

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3 Gener:1 ---- Sita QA

, Repr:sentztive Manager Technical Assistant Nuclear Plant Quality Administrative Supervisor Superintendent

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  • Manager eManager
  • Manager -

Plant Plant

- Plant '

Operations Maintenance Support Technical Technical Technical Assistant Assistant Assistant l I I I Materials _

Training

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Superintendent Industrial Technical Gemistry/ %MW Safety -fperations - Support - Radiation Control Superintendent Superintendent Coordinator SaPerintendent Mechanical _

_. Accountant og Radiation Superintendent operations Startup Supervisor

- Control Assistants Supervisor Plant ,

16C

- Secarity Fire bactor Nuclear Superintendent

, Supervisor _ Protection - Engineering _ Plant

  • Coordinator Supervisor Chemist Electrical ._

compliance Superintendent Superintendent Radwaste Technical .

3. Supervisor - Engineering Supervisor i ' Office Contracts
- Services } mg Supervisor Superintendent LShift Superintendents Shift Technical . _ .

Advisors Lines of Responsibility g

Shitc Lines of Communication Supervisors

  • Must have been SRO or have been l certified on a plant of this type. Nuclear Figure 6.2.2-1 operators A UNIT ORGANIZATION I I operator Nuclear Auxilliry Plant Operators B Operators Trainees 1

i . .

ADMINISTRATIVE CONTROLS INDEPENDENT SAFETY ENGI"NEERING GROUP (ISEG) (Continued)

RESPONSIBILITIES 6.2.3.3 "The ISEG shall be respon'sible for maintaining surveillance of unit

activities to provide independent verification
  • that these activities are performed correctly and that human errors are reduced as much as practical.

AUTHORITY .

6.2.3.4 The ISEG shall make detailed recommendations for revised procedures,

equipment modifications, maintenance activities, operations activities or other means of improving unit safety to the Assiste..t Vice President,fer Nuclear.
7. ,,,:.cti =. %amor

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6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide technical support to the i Shift Superintendent in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to safe operation of the unit.

6.3 UN T STAFF QUALIFICATIONS

6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions and the supplem
requirements specified in Section A and C of Enclosure 1 of the March 28, 1980
NRC letter to all licensees, except for the Chemistry /end. Radiation N
t:: tin /

, Superintendent who shall meet or exceed the qualifications of Regulatory Guide

, _ 1.8, Sootember 1975: the$hiftTechnicalAdvisorwhoshallmeetorexceedthe

quaH fications referred to in Section 2.2.1.b of Enclosure I of the October 30, l 1979 NRC letter to all operating nuclear power plants; and the members of the Indeoendent Safety Engineering Group, each of whom shall have a Bachelor of

, Science degree or be registered as a Professional Engineer and shall have at

least two years experience in their field, at least one 3 ear of which experience shall be in the nuclear field. -

6.4 TRAINING l 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Superintendent, shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified

, in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all Ifeensees, and shall include familiarization with relevant industry operational experience.

i 6.5 REVIEW AND AUDIT

6. 5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC)

FUNCTION '

GGNS Geotred 6.5.1.1 The PSRC shall function to advise the+1ent Manager on all matters l

related to nuclear safety.

N Not responsible for sign-off function.

GRAND GULF-UNIT 1 6-6

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4 ADMINISTRATIVE. CONTROLS PLANT SAFETY REVIEW COMMITTEE (PSP Q (Continued)

, COMPOSITION 6.5.1.2 The PSRC shall be composed of the:

I Chairman: h;htent Ph t Manager, %4 Oparoh*M

  • Vice Chairman: "rc h:r S;;:rt Manager, 9 tant Edana.nc.e -

. Member: Operations Superintendent Member: Technical Support Superintendent Member: Quality Superintendent cm.nvre\

Member
Chemistry /endRadiationT.;ectuaSuperintendent Member: I.j C ": St:::n:; Superintendent f9 amber: Technical Egneumg hparvisor i ALTERNATES GGMS Genaro-l 6.5.1.3 All alternate members shall be appointed in writing by the ++snt Manager l to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSRC activities at any one time.

MEETING FREQUENCY 6.5.1.4 The PSRC shall meet at least once per calendar month and as convened by the PSRC Chairman or Vice Chairman.

i QUORUM 6.5.1.5 The minimum quorum of the F3C necessary for the performance of the PSRC responsibility and authority provisions of these Technical Specifications

, shall consist of the Chairman or Vice Chairman and four members including alternates.  ;

RESPONSIBILITIES 6.5.1.6 The PSRC shall be responsible for review of:

/, s. Station administrative procedures and changes thereto.

b. The safsty evaluations for 1) procedures, 2) changes to procedures, equipment or systems, and 3) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did i not constitute an unreviewed safety question and all programs require,d by Specification 6.8 and changes thereto.
c. Proposed procedures and changes to procedures, equipment or systems t.hich may involve an unreviewed safety question as defined in
Section 50.59, 10 CFR.
d. Proposed tests or experiments which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

! e. Proposed changes to Technical Specifications or the Operating License.

GRAND GULF-UNIT 1 6-7

1 e  :

l

. ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

f. Reports of violations of codes, regufations, orders, Technical

. Specifications, or Operating License requirements having nuclear

, safety significance or reports of abnormal degradation of systems 4

designed to contain radioactive material.

g. Reports of significant operating abnormalities or deviations from -

normal and expected performance of plant equipment that affect nuclear safety.

h. All written reports concerning events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.
1. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.

. j. The plant Security Plan and changes thereto.

k. The Emergency Plan and changes thereto. -
1. Items which may constitute a potential nuclear safety hazard as l

identified during review of facility operations.

I a. Investigations or analyses of special subjects as requested by the i Chairman of the im. lee.- Safety Review Committee. I

n. The unexpected offsite release of radioactive material and the report j as describe <t in 6.9.1.13(e).
o. Changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION I

MANUAL, and radwaste systems.

AUTHORITY 6.5.1.7 The PSRC shall:

GGN5 Getiere.l

s. Recommend in writing to the Mont Manager approval or disapproval of l

. items considered under 6.5.1.6(a), (c), (d), (e), (j), and (k),

above.

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  • i b. Render determinations in writing to the Men Manager with regard to l whether or not each item considered under 6.5.1.6(a), (c) and (d),

above constitutes an unreviewed safety question. .

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> te the SRC of disagreement between the PSRC and the Mont Manager; howe'.or, the g $ gene M ? lent Manager shall have responsibility for esolution of such disagreements pursuant to 6.1.1 above. -

ggg 4 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.

Copies shall be provided to the SRC.

GRAND GULF-UNIT 1 6-8

't  :

1 ADMINISTRATIVE CONTROLS '

6.5.2 SAFETY REVIEW COMMITTEE (SRC)

FUNCTION 6.5.2.1 The SRC shall function to provide independent review and audit 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 COMPOSITION 6.5.2.2 The SRC shall be composed of the:

i Chairman: Vice President,4uclear Su.PPort Member: Mana f l

Member: Direckpr,;;ger,# Nuclear

r Of Quality Plant Engineerin Assurance Member
Designated Representative, M e South Services. Inc.

Me . . !h .r $rvi Direck, Nuclar Lu.tnunf N' Member: Manager,mi" Radiological b;; Environmental Services Member: Principal Engineer, Operationt Analysis Member:* Advisor to the Vice PresidentJNuclear opero. hens l l Two or more additional voting members shall be consultants to Mississippi t

' Power and Light Company consistent with the recommendations of the Advisory l

Committee on Reactor Safeguards lettsr, Mark to Palladino dated October 20, 1981.

The SRC members shall hold a Bachelor's degree in an engir.eering or physical science field or equivalent experience and a minimum of five years of technical ,

experience of which a minimum of three years shall be in one or more of the '

l

,, disciplines of 6.5.2.la through h. In the aggregate, the membership of the committee shall provide specific practical experience in the majority of the disciplines of 6.5.2.la through h.

i ALTERNATES

, 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basts; however, no more than two alternates

{ shall participate as voting members in SRC activities at any one time.

l

! "Non voting member.

4 GRAND GULF-UNIT 1 6-9 Amendment No. 9

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ADMINISTRATIVE CONTROLS AUTHORITY -

6.5.2.9 T.he SRC shall report to and advise the Senior Vice President I uclear N

l onthoseAreasofresponsibilityspecifiedinSections6.5.2.7and6.$.2.8.

RECORDS.

6.5.2.10 Records of SRC activities shall be prepared, approved and distributed ,

as indicated below:

a.

Minutes to the Seniorof each SRC meeting Vice President [shall Nuclear be14 within prepared, approved days folic.ing each and l f meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be
prepared, approved and forwarded to the Senior Vice President [ l 1 Nuclear within 14 days following completion of the review
c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President / Nuclear and to 'the l management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

. 6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

a. Procedures required by Technical Specification 6.8 and other procedures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by an individual / group other than the individual / group which prepared the procedure or procedure change, but who may be from the same organization as the individual / group which prepared the procedure or Procedures other than Administrative Procedures shall I GGNS Geotrol, be procedure approvedchange.

as delineated in writing by th M ur.t Manager. The G ee. l.:

Manager shall apprpve administrative procedures, security implementing -

h* Pb m) procedures and emergency plant implementing procedures. Temporary approval to procedures which clearly do not change the intent of the e approved procedures may be made by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License.

i For changes to procedures which may involve a change in intent of the i approved procedures, f.he person authorized above to approve the proca-dure shall approve the change,

b. Proposed changes or modifications te plant nuclear safety-related str;ctures, systems and components shall be reviewed as designated
G6NS Ged by theN Manager. Each such modification shall be reviewed by an Individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual'/ group which designed the modifica.tions. Implementation of proposed modifications to plant nuclear safety-related structures, systems and components shall be approved by the thmt Manager.

MNS GaAe. rod GRAND GULF-UNIT 1 6-12

c.

ADMINISTRATIVE CONTROLS _

ACTIVITIES (Continued)

c. Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Final Safety Analysis Report shall be reviewed '

.by an individual / group other than the individual / group which prepared the proposed test or experiment.

d. ' Occurrences reportable pursuant to the Technical Specification 6.9 and violations of Technical Specifications shall be investigated .

and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence. Such report shall be approved by the -Ment Manager and forwarded to the Chairman of the l Safety Review Committee. N Gags General

e. Individuals responsible for reviews performed in accordance with 6.5.3.1.a. 6.5.3.1.b, 6.5.3.1.c and 6.5.3.1.d shall be members of l

, the plant staff who meet or exceed the qualification requirements i , of Section 4.4 of ANSI 18.1, 1971, as previously designated by the

! GGNS GaA*rn.1 Med Manager. Each such review shall include a determination of l whether or not additional, cross-disciplinary review is necessary.

If deemed necessary, such r'eview shall be performed by the review personnel of the appropriate discipline.

l f. Each review shall include a determination of whether or not an unreviewed safety questica is involved. g3 gg

g. Records of the above activities shall be provided to the-Ct:ti: . l Manager, PSRC and/or as necessary for raquired reviews.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTA3LE OCCURRENCES:

a. The Cosaission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
b. Each REPORTABLE OCCURRENCE requirint, 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PSRC and submitted to the SRC andtheSeniorVicePresident[ Nuclear. l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Senior Vice President,# Nuclear and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l
b. A Safety Lielt Violation Report shall be preca.'ed. The report shall be reviewed by the PSRC. This report shall oescribe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems or structures, and (3) corrective action taken to prevent recurrence.

l GRAND GULF-UNIT 1 6-13

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