ML20151H814
| ML20151H814 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/18/1988 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20151H812 | List: |
| References | |
| NUDOCS 8808020060 | |
| Download: ML20151H814 (7) | |
Text
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A'ttachmont II _to Doc unent' Control Desk
. July 18. 1988 Page'1 of 6 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY o,.,, s u. -,, -
6.1.1 The-Meectee, Nuclea,r Plant Operations shall be responsible for overall unit operation and shall delegate in wri. ting the succession to this responsi-4 bility during his absence.
TA+-4?t i c-O u e c.st,- Nud4ea'e-P4 ant-Coe ea t4 ens A synonymous-to-the-ttttes-Hanegeer-Vi rwii C. 5umer-Muelear-Stat 4Mtation Manager-or-M ent-tiarraver.
6.1. 2 The Shif t Supervisor shall be responsible for unit operations.
A management directive to this effect, signed by the Vice Prasident, Nuclear Operations, shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organi:ation for unit manag3 ment and technical support shall be as shown on Figure 6.2-1.
UNIT STAFF 6.2.2 The unit organi:ation sh'all be as shown on Figure 6.2-2 and:
c.
Each on-daty shif t shall be composed of at least the minimum shif t crew composition shown in Table 6.2-1.
b.
At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor.
In addition, while the unit is in MODE 1., 2, 3 or 4, at least one Lic'ensec Senior Reactor Operator shall be in the Cor. trol Room.
A haalth physics technician # shall be on site when fuel is in the c.
- reactor, d.
All CORE ALTERATIONS shall be observed and directly sucervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation, A site Fire Spigade of at least 5 members shall be maintained ons'te e.
at all times.
The Fire Brigade shall not include the Shift Sucervisor and the other 2 members of the minimum shift crew necessary for safe shutdown of the unit cnd any personnel required for other essential functions curing a fire emergency.
- 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 unexoected absence provided immediate action is taken to fill the required positions.
SUMMER - UNIT 1 6-1 Amencment No. la 8308020060 (380718 PDR ADOCK 05000395 p
PDL j
' At.tachstent II to Docunent Conbl sk July 18, 1988
.Pago,2 of 6 t'"11NISTRATIVE CONTR0t.S Administrative procedures shall be developed and implemented to limit the I.
working hours of unit staff who perform safety-related functions; e.g.,
senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.
Adequate shift coverage shall be maintained without routine heavy use of However, in the event that unforeseen probless require overtime.
substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:
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 /> a.
straight, excluding shift turnover time, b.
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, A break of at least eight hours should be allowed between work c.
periods, including shift turnover time, Except during extended sh'utdown periods, the use of overtime should be d.
considered on an individual basis and not for the entire staff on a shift.
& e.,a r e I h t ~ p.,
Any deviation from the above guidelines shall be authorized by the 4irect m Nuclear Plant Operations or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis Except during extended shutdown periods, con-for granting the deviation.
trols shall be included in the procepur.g"sc) die, bat individual overtimeah Plant Op
[
f
- j shall be reviewed monthly by the 4feeche., 7 u Routine designee to assure that excessive hours have not been assigned.
deviation from the above guidelines is not authorized.
Amendment No. & 51 SUM ER - UNIT 1 6-la
l
.Att'schment II to Document Control Desk July 18, 1988 l
Page 3 of 6 l
t ADMINISTRATIVE CONTROLS
(
l 6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC) l FUNCTION 6.5.1.1 The PSRC shall function to advise the-Mteettir, Nuclear Plant Opera-(
tions on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Plant Safety Review Committee shall be composed of the:
f
{
c-.. a4 a
-Meeeter,/ uclear Plant Operations or t
N Chairman:
g,,,,,,/ pr.y4eputy-Director, Operations and Maintenance IB Member:
Manager Operations Member:
Manager Technical Support Member:
Manager Maintenance Services Member:
Group Manager, Technical and Support Services Member:
Associate Manager, Health Physics or a Health Physics Supervisor ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PSRC Chairman to serve on a temporary basis; however, no more than two alternates including the Chairman's alternate, if applicable, shall participate as voting members in PShc 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 er his designated alternate.
l 1
QUORUM I
6.5.1.5 The minimta c,uorum of the PSRC necessaiy for the performance of the PSRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and three members including alternates.
RESPONSIBILITIES 6.5.1.6 The Plant Safety Review Cosmittet shall review:
(
a.
Station administrative procedures and changes thereto, b.
The safety 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 not constitute an unreviewed safety question and all programs
(
required by Specification 6.8 and changes thereto, c.
Proposed procedures and changes to procedures, equipment or systems which 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 cefined in Section 50.59, 10 CFR.
Proposed changes to Technical Specifications or the Operating License.
e.
SU1NER - UNIT 1 6-6 Amendm.t No.18
l Mtachnent II to Doctrcnt Control Des!t
, July 18, 1988
- Page* 4 of 6 ADMINISTRATIVE' CONTROLS f.
Reports of violations of codes, regulations, orders, Technical Specifications, or Operating License requirements having nuclear safety significance or reports of abnomal degradation of system designed to contain radioactive material, Repor:s of significant operating abnormalities or deviations from d
g, normal and expected performance of plant equipment that affect nuclear safety.-
h.
Review of all REPORTA8LE EVENTS.
i.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or compone_nts.
j.
The plant Security Plan and changes thereto.
, k.
The Emergency Plan and changes thereto.
1.
Items which may constitute a potential nuclear safsty hazard as identified during review of facility operations, Investigations or analyses of special subjects as requested by the s.
Chairman of the Nuclear Safety Review Comittee.
The unexpected offsite release of radioactive material and the n.
report as described in 10 CFR 50.73.
Changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION o.
MANUAL.
AUTHORITY 6.5.1.7 The Plant Safety Review Comittee shall:
G a.. t W -y * *1 l
Recomend in writing to the Oleteteg Nuclear Plant Operations a.
approval or disapproval of items considered under 6.5.1.6a, c, d, e, j, and k above.
Render determinations in writing to the 44eeet+[Nu lear Pit,nt l
b.
Operations with regard to whether or not each item considered under 6.5.1.6a, c, and d above constitutes an unreviewed saftty question.
Make recomendaticas in writing to the hiYt+I.TuMear Plant
/
c.
Operations that actions reviewed under 6.5.1.6(b) above did not constitute an unreviewed safety question, d.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President, Nuclear Operations and the Nuclear afetyjoviewCommitteeofdis-agreement begeen QQP ff and the Wwef"$% Tear Plant Operations however, the MOhNNudlear Plant Operations shall have responsi-i bility for resolution of such disagreements pursuant to 6.1.1 above.
RECOROS
- 6. 5.1. 8 The Plant Safety Review Committee shall maintain written minutes of each PSRC meeting that, at a minimum, document'che results of all PSRC activ-ities performed under the responsibility and authority provisions of these technical specifications.
Copies shall be provided to the Vice Presidint Nuclear Operations and the Chairman of the Nuclear Safety Review Committee.
SLM ER - UNIT 1, 6-7 Amendment No, 35
.At'tcchment TI to nocument Control Desk July 18, 1988 Page 5 ej 6 ADMINISTRATIVE CONTROLS l
RECOR05 6.S.2.10 Records of NSRC activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each NSRC meeting shall be prepared, approved and fo Narded to the Vice President, Nuclear Operations within li days following each meeting, b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be pre-pared, approved and forwarded to the Vice President, Nuclear Opera-tions within 14 days following completion of the review.
c.
Audit summary reports encompassed by Section 6.5.2.8 above, shall be forwarded to the NSRC and to the Vice President, Nuclear Operations.
Full audits shall be forwarded to the management positions responsi-ble for the areas audited within 30 days after complation cf 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 folicws:
a.
Procedures required by Technical Specification 6.8 and other proce-rares which affect plant nuclear safety, and changes thereto, shall De 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 procedure change.
Procedures other than AdminJJ,,tgapige P[ocedures will be approved ag. Ag),,ipja,,t,3d,jn writing by the 4lrectee, 'N6 clear Plant Operations.
The Oirector,iluclear Plant
{
Operations will approve administrative procedures, security irrplement-l ing procedures and emergency plan implementing procedures.
Temporary approval to procedures which clearly do not change the irtent of the approved procedures can be made by two members of the plant managennt staff, at least one of whom holds a Senior Reactor Operator's License, For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the proce-dure shall approve the change, b.
Proposed changes or modifications to plant nuclear safety-related the 4 " ' pstems and components shall be reviewed as designated by struc res
, M iiar Plant Operations.
Each such modification shall be designed as authorized by Technical Services and shall be reviewed I
by an individual / group other than the individual / group whien designed the modification, but who may be frota the same organization as the indisidual/ group which designed the modifications.
Implementation of modifications to plant nuclear safety 3,t,3d p,t,,r,,tures, systems and 1
components shall be concurred in by the ucfor uclear Plant Operations.
SU M ER - UNIT 1 6-11 Amendx.ent No. % 49
'Attcchment II to Document Control Desk July 18, 1988 Pago 6 of*6 l
ADMINICTRATIVE CONTROLS 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.
Events reportable pursuant to the Technical Specification 6.9 and
~
violations of Technical Specifications shall be investigated and a riport prepared which evaluates the event and which provides recom-mendgtiong}pproventrecurrence.
Such report shall be approved by the -Jfiber, Tc' Tear Plant Operations and forwarded to the Chair-man of the Nuclear Safety Review Committee.
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 the plant staff that meet or exceed the qualification requirepents oj#f j.
i Sec-tion 4 of ANSI 18.1, 1971, aspreviouslydesignatedbytnPKddL l
Nuclear Plant Operations.
Each such review shall include a determina-(
i tion of whether or not additional, cross-disciplinary, review is ne-I cessary.
If deemed necessary, such review shall be performed by the t
i review personnel of the appropriate discipline, i
f.
Each review will include a determination of whether or not an unreviewed safety question is involved.
ks d lifa g t~
j 6.5.3.2 Records of the above activities shall be provided to the Director.
lL j
Nuclear Plant Operations, PSRC and/or NSRC as necessary for required reviews.
i 6.6 REPORTABLF EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
L a.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and i
b.
Each REPORTABLE EVENT shall be reviewed by the PSRC and the results of this review shall be sub.aitted to the NSRC and the Vice President, l
Nuclear Operations.
+
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is i
violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.
Tha Vice President, Nuclear Operations and the NSRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, r
i b.
A Safety Limit Violation Report shall be prepared.
The report shall j
be reviewed by the PSRC.
This report sha11 describe (1) applicable circumstances preceding the violation, (2) effects of the violation 1
upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence, c.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRC and the Vice President, Nuclear Operations within 14 days of the violation.
SLM4ER
'JNIT 1 6-12 Amendment No. 35,57 l
__v___--,--
.' httgehment!!!toDocumentControlDesk July 18 1988 P; p P o'f 1 ADMINISTRATIVE CONTROLS h
6.2.3 INDEPENDENT SAFEYY ENGINEERING GROUP (ISEG)
- FUNCTION,
- 6. 2. 3. 7.
The ISEG shall function to e': amine plant operating characteristics NRC issuances, industry advisories, L&ansee 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 specialists.
RESPONS!BILITIES 6.2.3.3 The ISEG shall be responsible for maintaining s7rveillarice of plant activities to provide independent verification
- that these activities are parformed correctly and that human errors are reduced as much as practical.
AUTHORITY
[
6.2.3.4 The ISEG shall make detailed recommendations for procedure revisions, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to the Group Manager, Technical Services.
6.2.4 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor shall provide technical support to.the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.
_6. 3 UNIT STAFF QUAL.IFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positions and the supplemental require-ments specified in Sections A and C of Enclosure 1 of the March 28, 1980 letter to all licensees as clarified in NUREG-0737 Section I.A.2.1, except for the Associate Manager, Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1.8 September 1975, the Shift Technical Advisor who shall meet or exceed the qualifications referred to in Section 2.2.1.b of Enclosure I of 2
the October 30, 1979 NRC letter to all operating nuclear power plants, and the members of the Independent Safety Engineering Group, each of whom shall have a,
Bachelor of Science degree or registered Professional Engineer and at least two years experience in their field.
At least one year experience shall be in the nuclear field.
- 6. 4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained and shall meet or exceed the requirements and recommendations of Section-5r5-of-ANSI-N18rl-1971 and-Appendix 8ALef-10 CER:Part4&:and the supplementakequirements-specified-irt-Sections-A and-C-of-Enclosure--l-of-the Ha rd-28 r-1980-NRC-l e t t e rte-e l H 4 ee ns e e s,-end -s ha l l-i n cl ude-f ami l i a r i z a t io n-win-identifl etral e vant4 adu s t ry-ope ra t i onal-experi e nc e,
*" 5. 2 s.<d S's' o f 4 az 3.i., yyi,,J icymg,r,r p7,,_,,,,,,p;.u.
h~
"Not responsible for sign-off function.Ag c~4 M, f n f..;../ s.f, G A.,4 Repad.
SumER - UNIT 1 6-5 Amendment No. 36