ML19323C767
| ML19323C767 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/16/1977 |
| From: | Desiree Davis Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19323C736 | List: |
| References | |
| FOIA-80-162 NUDOCS 8005190158 | |
| Download: ML19323C767 (12) | |
Text
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8 00519 015F O
C015@ERS P%ER CN9EY DCCKET t:9. 50-155 iiIG ROC PSIHT PLANT AMDG'E::I TO FACILITY OPERATIPS LICENSE f
~
Enandment !!c.
Il License 30. DPP-G l.
The N9 clear ?.egulatory Cerr.lission (the Crvcissian) ois found that:
The aprlication for anenenent by the Consulars Power Ccs.7any A.
e (the licensee) itated March 8,1976, as nodif.ied by letter dated
!> arch 3,1977, complies with the standards and requiretents of the Ato;11c Energy Act of 1954, as elenced (the Act), and thq Connission's rules and regulations set forth in 10 CFR Chapter I; j
D.
The facility will operate in conforaity with the application, the provisions of the Act, and the rules and regulations of the Con >11ssion; C.
Tnere is reasonable assurance (1) that the activities authorized by this amendment can se conducted without endangering the health and safety of the public, and (ii) tilat such activities will be conducted in conpliance pith the Connission's reculations; D.
The issuance of this acendment will not be ininical to the co= ton defense and security or to the health and safety of the public; and E.
Tlie issaance of this cuendaent is in accordance with 10 CFR Part 51 of the Coanission's regulations and all applicable requirements have been satisfied.
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/,ccordincly, t::e i f,:ense is a 1:nded by chance" to tne Technical N
Specifications as indicatsd in the a!.tachrier.: to this license a'.'encr.ent and.paragraoh 2.C(2) of facility License No. DPR-6 is hereby c' aned to read as follows:
(2) Technical Specifiertions The Technical Specifications. contp as revised through Aneniment he. 2 joc1 in /ppendix t,
, are hereby incornorated in the licens?.
The licensee'shall operate the facility in accoraance witu the Technical Specifications.
3.
This license anendnent is effective as of the state of its issuance.
FOR THC MUCLEAR REGULATORY C0fliiISSION Or icj i b d G i p c[4 i
Dmk.06 Don K. Davis, Acting Chief Operating Reactors Branch 42 Division of Operating Reactors A.ttschr. cat:
Changes to tne Technical Specifications Date of Issuance:
g.,1S 1977 orrecs >
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NRC PORM 318 (976) NAN 0240
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ATTACHMENT TO LICENSE AMENDMENT NO. 12 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155
,1.
Replace the following pages of the Technical Specifications contained in Appendix A of the above-indicated license with the attached pages bearing the same numbers, except as otherwise indicated.
The changed areas on the revised pages are reflected by a marginal line.
Remove Insert 111 iii 10-2 (Figure 6.2-1) 10-2 (Figure 6.2-1) 10-3 (.
10-4(iigure6.2-1) 10-3 (Figure 6.2.2 10-4 (Taole 5.2-1))
aaole 6.2-1) 10-5 10-5 10-7 10-7 10-8 10-8 10-10 10-10 10-11 10-11 2.
Add new Specification 1.1.4 as follows:
Surveillance requirements shall be applicable as specified for individual components or systems as stat.ad in individual specification requirements.
Each surveillance requirement shall be performed within the spee fied time d
interval with:
a.
A maximum allowable extension not to exceed 25% of the surveillance
- interval, b.
A total 70ximum combined interval time for any three consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.
I-C0ffrEN t, Iontd)
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Page No.
7.0 Operating Procedures.
7-1 T.1 Deleted.
'72 Deleted........................................
7 2.1 Deleted........................................
7 2.2 Deleted.
7.2.3 Deleted.
7.2.h Administrative and Procedural Controls Relating to liigh Performance Fuel 7-3 73 Normal operation 7-3 7.3.1 General........................................
7-3 7.3.2 Cold Start-Up After Extended Shutdown..
7-3 7 3.3 llot Start-Up 7-4 7 3.5 Extended Shutdown...................................
7-5 7.3.6 Short Duration Shutdown................................
7-6 0
7.h Refueling Operation.
7-6 75 Maintenance (Deleted Except for 7 5.7) 7-8 7.6 Operational Testing of Nuclear Safeguard Systems 7-8 77 Deleted.
8.0 Research and Development Program.
8-1 8.1 Developmental Fuel Design Features 8-1 3.1.1 Zr-Cr Alloy Test Bundle.~.
8-1 8.1.2 Thin Clad Power Fuel Bundle.
8-5 8.2 Principle Developmental Fuel Operating Limitations B-5 8.2.1 Center Melt Test Fuel Bundles.............................
8-5 90 Primary System Surveillance 9-1 10.0 (Section 6.0) Administrative Controls 10-1 6.1 Responsibility 10-1 j)
.2 Organization 10-1 6.2.1 Off Site 10-1 6.2.2 Plant Staff......................................
10-1 6.3 Plant Staff Qualifications 10-1 6.h Training 10-5 6.5 Review and Audit 10-5 iii
/FraaCamREAJL 12
Consumers Power Company OFF-SITE ORGANIZATION PRESIDENT EXECUTIVE VICE PRESIDENT l
SAFETY AND AUDIT VICE PRESIDENT REVIEW PRODUCTION & TRANSMISSION BOARD I
I I
1 MANAGER OF MANAGER OF DIRECTOR OTilER PRODUCTION-NUCLEiR MAINT &
ASSU CE ADM SERVICES pgy Q
PLANT GENERAL SUPT OA SUPERINTENDENTS ADM SERVICES ADMINISTRATOR (NUCLEAR)
NUCLEAR TRAINING ADMINISTRATOR o
FIGURE 6.2-1 Amendment No. 9, 12 D@@
Consumers Power Company BIC ROC,K POINT Organization t
QA-ADMIll 0FF-SITE Pl. ANT SUPEk1NTENDENT PLANT KEVIElf CollHITTEE QA SUPT I
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PERSONNEL TECllNICAL DIRECTOR ENGINEER TRAINING OPERATIONS ADMINISTRATIVE IIEALTil TECilNICAL HAINTENANCE COORDINATOR SUPERINTENDENT SUPERVISOR PilYSICIST SUPERINTENDENT SilPERINTENDENT SOL (a)
IEC ANCE EHCINEElt SECURITY CilEll & RAD ENGINEEllS TRAINING OPEETIONS l
C 1 N Yr0R A"
ENCI" "
QC INSTRUCTOR SUPERVISOR
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INSPECTOR 16C SOI. (b)
HAIN.TENANCI SUPEltVISolt SilPEttVISolto PLANT Silll~r
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^
l l' AN T i
SUPERVISORS ENGINEER ASSISTANT l
HAlNTENAtlCE TECilNJ Q!!S SUPERVISoll WCHEER OPERATORS REPAlltHEN SOL - Senior Operator Licensee (c) The Opernt.lonu Superintendent, need not hold un UOL provided he meeLu the other requiremenLu of 6.3.1 of thene specifications and the posillon of " Operations Suporvloor" la filled. Under I.hese conditiono, the Opernt.lona Supervisor shall be responsible for direcLing the activities of licenseil operators.
j (b) Tlits posit.lon need not be filled if the Operationn Superintendent holds un 30L.
Figure 6,2-2 Amendment No. 9, 12 10-3
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i L
TAllLE 6.2-1 Minimtua Lhift Crew Composition The minimum shift crew shall be as follows except when plant conditions specified in paragraph (a) or (b) below have been established (see note (1) below) or when an unexpected absence occurs (see note (2) below):
1 Shift Supervisor - SOL 2 Operators - OL 1 Operator - Nonlicensed
'O (a) Cold Shutdown 1 Shift Supervisor - SOL 1 Operator - OL 1 Operator - Nonlicensed (b) Refueling Operations ;See note (3) below) 1 Shift Supervisor - SOL 1 Operator - OL 2 Operators - Nonlicensed
^
O SOL - Senior Operator Licensed in accordance with 10 CFR 55.
OL - Operator Licensed in accordance with 10 CPR 55.
(1) During control rod motion associated with reactor start-up (to a power level 2 5 percent), one licensed Operator shall observe the control rod manipulation to ensure established control rod withdrawal pre cedures are adhered to.
(2)
In t.he event that any member of a minimum shif t crew is ubsent or incapacitated due t,o illness or injury, a qualified replacement shall report on site within t.vo hours.
(3)
Does not include additional personnel required when core alt erationu are being conducted. ::ee 6.;?.;?.e.
Amendnent No. 7,12
6.4 TRAINING 6.h.1 A retraining and replacement training program fbr the plant staff shall be maintained under the direction of the Nuclear Training Administrator and shall meet or exceed the requirements and recommendations of Section 5 5 of ANSI H18.1-1971 and Appendix "A" of 10 CFR, Part 55 6.5 REVIEW AND AUDIT 6.5 1 _ PLANT REVIIM COMMIT 1'EE (PRC) 6.5.1.1 FUNCTION The Plant Review Committee (PRC) shall function to advise the Plant Superintendent on all matters related to nuclear safety.
6.5.1.2 COMPOSITION
~
The PRC.shall be composed of the:
Chairman:
Plant Superintendent Member:
Operations Superintendent Member:
Technical Superintendent Member:
Maintenance Superintendent Member:
Instrument, and Cont rol Engineer Member:
Reactor Engineer Member:
IIcalth Physicist.
Member:
Shift Supervisor
()
Member:
Engineer or Technologist With at Least One-Year Plant Experience 6.5.1.3 ALTERNATES Alternate members shall be appointed in writing by the PRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in PRC activities at any one time.
nendnent No, p 12
s 6.5 1 (Cont'd) 6.5 1.7 Atrrl!ORITY The PRC shall:
Recommend to the Plant Superintendent written approval or disapproval of' items a.
considered under 6.5 1.6(a) through (d) above.
Hender determinations in writing with regard to whether or not each item considered l
b.
under 6.5 1.6(a) through (c) above c,onstitutes an unreviewed safety question.
D Provide immediate written notification to the Manager of Production, Nuclear and
.the Chairman of SARD of disagreement between the PRC and the Plant Superintendent.
c.
However, the Plant Superintendent shall have responsibility for resolution of such diungreements pursuant to 6.1.1 above.
6.5 1.8 RECORDS The PRC shall maintain written minutes of each meeting and copies shall be provided to the Manager of Production, Nuclear, the Chairman of SARB, PRC members and alternates.
6.5.2 SAPI?PY AND AUDIT REVIIM BOARD (SARB) 6.5 2.1 BCSPOtiSIBILITIES SARB is responsible for maintaining a continuing examination of designated plant activities.
In all cases, where a matter is formally considered by SARD, its findings and recommendations f
are communicated in writing to the Vice President - Production & Transmission (P&T) and other A written charter is prepared and approved by the Vice appropriate 1cvels of manngement.
President - P&T which designates the membership, authority and rules for conducting the Board membership, qualifications, meeting frequency, quorum, responsibilities, meetingc.
authority and records are in accordance with the nuclear plant Technical Specifications and ANSI N18.7-1972.
s 6.5 2.2 FUNCTION The SARD shall function to provide independent review of designat',ed activities affecting safety-related components, systems and structures designated on the plant's Safety-Related Quality List contained in the Consumers Power Company Quality Assurance Program.
10-7 Anmndment No. 9, 12
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6.5 2 (Cont'd) 6.5.2.3 COMPOSITION AND QUALIFICATIONS Collectively,- the personnel appointed for the SAR'B by the Vice President - P&T shall be competent to conduct reviews and technical audits in the following areas:
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.
An individual appointed to the SARB may possess expertise in more than one of the above specialties. lie should, in general, have had professional experience at or abo.ve the senior en61neer level in his specialty.
- 6. 5.2.16 ALTERNATE MEMilERS 0
Alternate members may be cppointed by the Vice President - P&T to act in place of members l
during any legitimate and unavoidable absences including a conflict-of-interest determination.
The qualifications of alternate members shall be similar to those members for whom they will substitute.
6.5.2.5 CONSULTANTS 1
Consultants shall be utilized as detennined by the SARB members and/or chairman to provide expert advice t,o the SARB.
SARB members are not restricted as to s-+ ces of technical input
)
and may call fbr separate investigation from any competent source.
10 8
6.5 2 (Cont'd) h.
The status of deficiencies identified by the Quality Assurance Program, including the effectiveness of t,he corrective actions completed and implemented, at, least, once every six (6) months.
- i. Audits of the Security Progrrus required by t.he " Nuclear Power Plant Securit.y Plan."
6.5 2.9 AUDPfS Audits of safety-related facility act.ivities during operations are perfonned by the Quallt.y Assurance Department. - P&T in accordance with the policies and procedures of t.he Constuners l
Power Company Quality Assurance Progrrun. Quality Assurance audit reports are sent to SAllB for review.
In addition, technical audit.s are t.he reuponulbilit,y of t.he Technical Services Depart. ment and shall be reviewed by SAltD. These technical audits encompass:
The honformance of facility operation t.o all provisions cont.nined within the Technical a.
Specifications and applicable license conditions at least, once per year.
b.
The perfonnance, training and qualifications of the entire facility staff at least once per year.
The facility Site Dnergency Plan and implementing procedures at Icast once per two years.
c.
Any ot.her area of facility operation considered approprint.e by SAHD or the Vice President - P&T.
d.
6.5 2.10 AttriloRITY_
i SARD shall report to and advise the Vice President - P&T on those areas of responsibility O
specified in 6.5 2.0 and 6.5.2.9 6.5.2.11 ItkcoIIIU Becords of SAllli act,1vlt,len shall be prepared and llut.rlbut ed as indicated below:
Minutes of each SAlll! meet,ing shall be prepared and forwarded t.o fl$e Vice President. - P&T nnd l
a.
cach SARB member wit.hin fourteen (li) days following each meeting. Minutes shall be approved l
at, or before the.next regularly scheduled meet.ing following distribution of t.he minut.cs.
If not included in GAlll? meet.ing minut.cu, reporta of reviewn encompnnsed by Sect. inn 6.5.2.8 b.
I nhove ahn11 he prepured und forwarded I.o t.hu Vice Prealdent. - P&T wi t.htn fourt.cen (18 )
8 dnyn following complet.it3n of t.he review.
0 10 10 g
-6.5 2 (Cont'd)
Audit reports encompassed by 6.5.2.9 above, shall be forwarded to the Vice President -
P&T and management positions responsible for the areas audited within thirty (30) days
{
c.
af ter completion of the aud,it.
6.6 REPORTAllLE OCCURHPNCE ACTION 6.6.1 The following actions shall be taken in the event of a reportable occurrence:
The Commission shall be imhiediately notified pursuant to 6.7 or a report submitted pursuant a.
to the requirements of 6.9 All events which are required by regulation or Technical Specifications to be reported to the,
((}
b.
NRC in writing within 214 hours0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br /> shall be reviewed by the PRC. The results of the PRC review shall be submitted (either by PRC minutes or by separate report) to SARB and the Manager of Production, Nuclear.
6.7 SAFWrY LIMIT VIOLATION 6.7 1 The following actions shall be taken in the event a Safety Limit is violated:
The reactor shall be shut down immediately and not restarted until Commission authorization a.
is received (10 CFH 50.36(c)(1)(1)].
The Snfety Limit violation shall be reported immediately to the Commisalon in accordance b.
with 10 CFH 50.36, the Manager of Production, Nuclear and to SAHl! Chairman or Vice-Chnirman.
A report chall be prepared in accordance with 10. CFR 50.36 and 6.9 or thls' specification.
c.
The Safety Limit violation and the report shall be reviewed by the PRC.
(}
The report shall be submitted within 10 days to the Comminnion (in accordance with the d.
requirements of 10 CFR 50.36), SARB Chairman and the Manager of Product' ion, Nuclear.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained for all structures, systems, components and safety actions defined in the Big Rock Point Quality List. These procedurca uhall meet or exceed the requirements of ANSI-18.7 10-11 i
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