ML20031A285
| ML20031A285 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/03/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031A284 | List: |
| References | |
| NUDOCS 8109220844 | |
| Download: ML20031A285 (16) | |
Text
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UN1'TED STATES j
%o 3-NUCLEAR REGULATORY COMMISSION j
j WASHINGTON, D. C. 20555 e
+
g CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. DPR-6 1.'
The Nuclear Regulatory Commission (the Commission) has found that:
A.
This application for amendment by Consumers Power Company (the licensee) dated February 16, 1981, as supplemented July 1,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate ir conformity with the application, the provisions of the Act, and the rules and regulations of theCommissionQ C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense,and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
kDR9 44 810903 p
K 05000155 PDR
2.
Accordingly, the licenseis amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Facility Operating License No. DPR-6 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specificatichs contained in Appendix A, as revised through Amendment No. 46, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of its issuance.
3.
FOR THE NUCLEAR REGULATORY COMMISSION I
y i
enn
. Crutch ield, C ef Operating Reactors Branc #5 Division of licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 3,1981 O
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ATTACHMENT TO LICENSE AMENDMENT NO. 46 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155 Revise Appendix A ' echnical Specifications by removing the pages identified T
below and inserting the enclosed pages. These revised pages include the captioned amendment number and contain-vertical lines indicating the area of change.
PAGES 10-1 10-la 10-2 (Figure 6.2-1) 10-3 (Figure 6.2-2) 10-4 10-5 10-6 10-7 10-8 10-9 10-10 10-11 10-12 i
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CONSUMERS POWER Cof1 patly OFF-FITE ORGAHlZATION f
PRESIDENT EX[CullVE EXECUIIVE VICE PitESIDENT j
VICEPRESIDENTl I
I VICE Pit [SIDENT SAFETY & AUDIT VICE PRESIDtNT HUCt.[ Alt OP[ftAil0NS HEVIEW DOARD C[H[RAL SERVICES Dlit[CIOR of PROPERIY pro 1ECTION" Oill[R DIRICIOR OF C[NEftAL I4GR GENERAL HGR P[ ANT S[ltVICES utIALlIY H I Dt. Attu PALISADES SUP[HINIENDENI BlC ft0CK PolNI I
ASSURANCE eHesponsible for Overall
{
Iiro Protection Program i
I Figure 6.2-8 a
10-2 AmendmentNo./f,fT, M, 46
CONSUMERS PC'iER COMPANY Plant Organization QA-NG Department Plant Superintendent Off-Site Big Rock (a)
I Plant Review Co=mittee QA Superintendent Operations &
Health Technical Maintenance Physicist Superintendent Superintendent I
1 i
Operatiens Maintenance Superintendent Superintendent or Supervisor or Engineer SOL (b)
Shift A.
Personnel knowledgeable in the following areas identified
' Supervisors in ANSI N18.7-1976/ANS 3.2 will report at the discretion SQL of the Plant Superintendent.
1.
Nuclear Power Plant Mechanical, Electrical and Electronic Systems.
2.
Nuclear Engineering.
3.
Chemistry and Radiochemistry.
4.
Radiation Protection (reports to the Health Physicist).
A single individual may be qualified and perform in more than ene discipline.
B.
The Security force will be supervised as described in the Plant Security Plan.
C.
Quality Control activities will be in accordance with the d
Consu=ers Power Quality Assurance Program Policies.
(a) Responsible for the Plant Fi:. Protection Program implementation.
Either the Operations Superintendent or the Operatiens Supervisor will hold an (b)
SOL and meet the other requirements of 6.3.1 of these Technical Specifications The individual holding (as applicable to Operations Manager in ANSI N18.1).
an SOL shall be responsible for directing the activities of licensed op-erators.
(SOL - Senior Operator Licensee)
Figure 6.2-2 10-3 AmendmentNo./,[,yI,}$,
46
r.
TABLE 6.2-1 tilajeum Slith_Grmw comeonitin:7 The minimum shift crow shall be as follows except when plant conditions specified in paragraph (a) or (b) below have been establishod (see Nnte (1) below) or when an unexpected absence occurs (soo Note (2) below):
l 1 Shi f t Supervi sor - SOL 2 Operators - OL
. l i
10 erator - Nonlicensed I Sbilf t Technical Advisor (STA) - Nonlicensed l
l a.
Egid_11tyLdgyg_ add ShutdoWD (As Defined by Seccion 1.2) l l
1 Shif t Supervisor - SOL 1 Opera tor - OL 1 Operatnr - Nonlicensed b.
Rg[ggljpg Oggr_aL{gns (See Note (3) Below)
I Shift Supervi sor - SOL 1 Opera tor - OL 2 Operators - Nonlicensed SOL - Senior Operator Licensod in accordance with 10 CFR 55.
OL - Operator Licensed in accordance with 10 CfH 55.
rod motlan associated with reactor start-up (to a power lovel 2 5 percent), one licensed operator shall (1)During control observe the control rod manipulation to ensure established control rod withdrawal procedures are adherod to.
(2)ln the event that any member of a alnimum shif t crew is absent or incapacitated stuo to fliness or injury, a qualfled replacement shall report on site within two hours.
(3)Does not include additional personnel required when core alterations are being conducted. See 6.2.2.e.
l l
l 1
i Ame'ndment No./,[, 46
/
10-4 t
s
(
6.h
'I1t AINI NG A retraining and replacement training program for the piant staff shall be meintained under 6.h.1 the direction of the Plant Superintendent and 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 A training program for the Fire Brigude shall be maintained under the direction of the Plant 6.h.2 Training Coordinutor und uhull meet or exceed the resguiremento or Section 27 of the NVI*A Code-1975 except for Fire urisade training :sssions which shall be held at least quarterly.
6.5 REVIEW AND AUDIT '
6.5.1 PIANT REVIEW COMMI'I' FEE (PRC)
The Plant Review Committee (PRC) shall function to advise the Plant. Superintendent on all 6.5 1.1 matters related to nuclear safety.
6.5 1.2 00MPOSITION The PRC shall-be composed of the:
Chairman: Plant Superintendent Member:
Operations Superintendent
- Member:
Technical Superintendent Member:
Maintenance Superintendent
- Member:
Operations Supervisor Member:
Instrument and Control Supervisor Member:
Reactor Engineer Member:
-lIcalth Physicist Member:
Shift 7upervisor Member:
Maintenance Engineer
- llhen these positions are combined in accordance witn the Plant Organization, Figure 6.2-2 the individual holding both positions serves as a single voting member of the PRC.
e
.I AmendmentNo.9,J2,77,Jg,jpt-46 10-5
6.5.1.3 At.TrRNATIS Afterpate members shall be appointed in wri ting by the PRC Cha i rman to serve on a tempo ra ry ba s i s; howeve r, no mo re than two alternates shall participate as voting members in PRC activities at any one time.
6.5. l. fi M!ntNG_LRrQUINCY T he PRC sha l l mee t a t least once per ca lenda r month with specia l PRC " cot ings a s requi red.
6.5.l.5 QUORUM A quorum of the PRC shall consist of the Chairman and four membos s (including alternates).
6.5.1.6 (tJ100NSinlLITIES The PRC shall be responsible for:
Review of: (1) All procedures required by Technical Specification 6.8 and changes thereto, and (2) any other a.
proposed procedures or changes thereto as determined by the PRC Chairman to af f ect nuclear safety.
b.
Review of all proposed tests and experiments that arrect nuclear safety, c.
Review of all proposed changes to the Technical Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that arrect nuclear sarcty.
e.
Investigation or all violations of the Technical Specifications. A report shall be prepared covering ovaluation and recommenda tions to prevent recurrence and forwarded to the Vice President-Nuclear Operations (NO) and to the Cha i rman of the Sa fety and Audi t Review Hoa rd ( SARB).
l-f.
Review of plant operations to detect potential nuclear safety hazards.
g.
Performance of special reviews and investigations and reports thereon as requested by the Chairman of SARB.
h.
Review of the plant Emergency Plan and implemeriting procedures and shall submit recommended changes to the rmergency Plan to the Chairman of SARB.
- i. Review or all events which are required by NRC Regulations or Technical Specifications to be reported to the NRC within 284 hours0.00329 days <br />0.0789 hours <br />4.695767e-4 weeks <br />1.08062e-4 months <br />.
10-6 Change Ho. pf,
~
Amendment No. 46
+
b 6.5.1.7 AUllinR I TY The PRC shall:
a.
Recommend in writing to the Plant Superintendent approval or disapproval or items considered under 6.5.1.6(a) l l
through (d) above.
b.
Render determinations in writing with regard to whether or not each i tem considered under 6.5. l.6( a) through (c) above constitutes an unreviewed safety question, Provide within 2fs hours written notification to the Vice President-Hucicar Operations and the Chairman ur SARB or c.
disagreements between the PRC and the Plant Superintendent. Itoweve r, the Plant Superintendent shall havo responsibility for resolution of such disagreements pursuant to 6.l.1 above.
6.5.1.8 BECORDS The PRC shall maintain written minutes or each meeting and copies shall be provided to the Vice President-Nuclear Operations and the Chairman of SARB, PRC members and a l terna tes.
6.5.2 SAFETY AliD AUDIT REVi[W BOARD (SARB_1 6.5.2.1
!![SPONSin t L I T i rs SARD is responsible for maintaining a continuing examination of designated plant activities. Ist all cases, whero a matter is formally considered by SARD, its findings at.d recommendations arn communicated in writing to the Vice President-Nuclear Operations (NO) and other approorlate levels or management. A written charter is prepared and approved by the Vice President-No which designates the membership, authori ty and rt,8 es fo r conduct ing the meetings.
SARB membership, qual.Tications, meeting frequency. quorum. responsibilities, authority and records are in accordance with the nuclear plant Technical Specifications and ANSI N18.7-1916.
6Property "ANSI code" (as page type) with input value "ANSI N18.7-1916.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..5.2.2 BlNCTION SARB shall function to provide independent review or designated activities in the areas specified in 6.5.2.3.
l Amendment No, g, y[, 46 10-7
i i
6.5.2.3 C__OMPOSITION AND QUltjuCATIONS Collectively, the personnel appointed for LARB t>y the Vice President-NO shall be competent to conduct reviews in the following areas:
a.
Nuclear Power Plant Operations b.
Nuclea r Engineering c.
Chemistry and Radiochemistry d.
Me ta l l u rgy e.
Instrumentation and Control r.
Radiologicti Safety g.
Mechanical and Electrical Engineering h.
Quality Assurance Practices An individual appointed to SARB may possess expertise in more than one of the above specialties. lie should, in gene ra l, have had professional experience at or above the Senior Engineer level in his specialty.
6.5.2.4 ALTEftMATE MEMRLRJ Alternate members may be appointed by the Vice President-NO to act in place or member.s during any legitimate and l
unavoidable absences including a conflict-or-interest determination. Iho qualifications or alternate members shall be I
similar to those members for whom they will substitute.
6.5.2.5 C_0XstjtTAlqS Consultants shall be utilized as determined by SARB members and/or the Chairman to provide expert advice to SARil.
SARil members a re not restricted as to so arces of technical input and may call for separatu investigation f rom any competent sou rce.
m 10-8 Amendment No, g, M, 46
~
J 6.5.2.6 t4filHC.fR Qt!GGY SARD sball meet at least once per calendar quarter during the initial year of racility operation rollowing ruel loading and at' least once every six months thercarter.
6.5.2.7 QUORUM A quorum of SARB shalI consist of the Chairman or his designateel alternate and four (8s) members or their alternates.
l line responsibility for operation or the racility, it is the No more' than a minority of the quorum shall have responsibility of the Chairman to ensure that the quorum convencd for a SAHD meeting contains appropriately qualified members or has at its disposal consultants sufficient to carry out the review functions required by the meeting agenda.
6.5.2.8 BGHW SARD shall review:
Proposed tests or changes to procedures, equipment a..J systems which are deemed to involve an unroviewed sarcty a.
question as defined in 10 Cril 50.59.
b.
Proposed changes in Technical Specifications or licenses.
that Significant operating abnormalities or deviations from normal and expected performance or plant equipment c.
arrect nuclear sarety.
d.
All events which are requi red by regulatloas or Technical Specifications to be repo rted to NHC in writing within 2fs hours and other violations (or applicabic statutes, codes. regulatiores, orders, lechnical Specifications, license requi rements or or interna l procedures or instructions) having nuclear safety significance.
deports and meeting minutes or the PRC including safety evaluations for changes to procedures, equipment or systems auch actions did not end tests or experiments completed under the provisions or 10 CIR 50.*>9 to vort ry that c.
constitute an unreviewed safety question, in Section 6.5.2.9 l
The results or actions taken to correct doriciencies identified by the audit program specirled l
f.
at least once every six months.
10-9 Change No. 4ff, Amendment No. 46 m
6.5.2.9 AUDITS Audits or operational nuclear safety-related racility activities shall be performed under the cognizance of SARB, The50 audiLs shai1 encompass:
The conformance or racility operation to provisions contair.v within the lechnica! Specifications and applicable a.
i license conditions at least once per 12 months.
b.
The performance, training and quallrications of the entire f acility starr at least once per 12 months.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria or c.
Appendix "O,"
10 CrR 50, at least once por 2ta months, d.
The racility Site rmergency Plan and implementing procedures at least once per 2ts months.
The s'acility Security Plan an'd implementing procedures (as required by the Security Plant at least once per 24 e.
months.
f.
Any other area or racility operation considered appropriate by SARil or the Vico President-NO.
g.
The racility fire Protection Program and implementing proceduros at least once per 2td months.
h.
An independent rire protection and loss prevention inspection and audit shall be performed annually utilizing either quallflod orr-site licensee personnel or an outside rire protection firm.
- i. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
reports encompassed by 6.5.2.9 above shall be fo rwa rded to the Vice President-HO and management positions Audit responsible for the areas audited within thirty (30) days arter completion or the audit.
6.5.2.10 AUTHORITY to and advise the Vico President-No on those areas or responsibility specified in Sections 6.5.2.8 SARB shall report and 6.5.2.9.
6.5.2.11 g[ CORD $
Records of SARB activit!es shall be prepared and distributed as indicated below:
Minutes of each SARB meeting shall be prepared and forwarded to the Vice President-HO and each SARB member within approximately two weeks rollowing the meeting. Minutes shall be approved at or before tne next regula rly scheduled a.
meeting rollowing the distribution or the minutes.
' Amendment No. JK y/,g, 46 10-10 e
b.
If not included in SARD meetif% minutos, reports or reviews encompassed by Section 6.5.2.8 above shin a l be prepa red and forwarded to the Vice Presidern
~.0 within approximately two weeks following completion of the review.
6.6 (Deleted).
6.7 SAFETY 1.lMIT VIOI.ATlog 6.7.1 1he rollowing actions shall be taken in the event a Saroty Limit is violated:
a.
The reactor shall be shut down immealately and not restarted until the Commission authorizes resumption or operation (10 CFR 50.36(c)(1)(i)).
b.
The Safety Limit violation shall be reported within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to the Commission in accordance with 10 CFR 50.36 to the Vice President-NO and to SARB.
c.
A report sha ll be prepared in accordance with 10 CFR 50.36 and 6.9 of this spect rication. The Safety Limit violation and the report shall be reviewed by the PitC.
d.
The report shall be submitted within 18s days to the Commission (in accordance with the requirements of 10 CFR 50.36) and to the Vice President-NO and to SARB.
6.8 PROCEDUR_[$
6.8.1 Written procedures shal s he established, implemented and maintained for all structures, systems, components and safety actions defined in the Hiy Rock Point Quality I.ist.
Those procedures shall meet or exceed the requirements of Af(Si N18.7-1976.
10-11 Amendenent No. 46 E,
a~
l 4
Each procedure and administrative policy or'6.8.1 above and changes thereto shall be reviewed by the PRC (except for 6.8.2 security procedures which are reviewed by the Company Property Protection Department) and approved by the Plant 1
j Superintendent prior to implementation.
6.8.3 Tempora ry changes to procedures or 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members (or designaied alternates) or the PRC, at Icast one or whom holds a Senior Reactor Opera tor's licenso.
c.
The change is documented, reviewed by the PRC at the next regularly scheduled meeting end approved by the Plant Supe rintenden t.
6.9 RrPORTING RfQUIErMrNTS 4
in addition to the applicable reporting require 6 of Title 10, code of federal Regulations. the following identified reports shall be submitted to the Director or
- .t
.propriate Reg!onal Orrice of Inspection and [nforcement unit ss j
otherwise noted.
6.9.1 RollTlHl; _ REPORTS S t a_rt-l>p Repor_t - A summa ry repo rt o r p l a n t s ta r t-up and powe r e sca l a t i on te s t i ng sha l l be submitted rollowing:
a.
(1) ReceM of an operating license, (2) amendment to the license involving a planned increase i n powe r l eve l,.
2 (3) installation or fuel that has a dirrerent design or has been manufactured by a dirrorent ruel supplier and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance or the plant.
The report shall address each of the tests identified i n the lla za rd s Summa ry Repo r t a nd sha l l, i n gene ra l, include a j
description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions ard specifications. Any corrective actions that were i
j required to obtain satisfactory operation shall also be described. Any additional specific detaills required in license conditions based on other comnitments shall be included in this report.
3 be submitted within: (1) 90 days following completion or the start-up tast program, Start-Up Reports shall (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months rollowing initial criticality, whichever is earliest. t r the Start-Up Report does not cover all thrtas events ( ie, initial criticality, completion of start-to test program, and resumption or commencement or commercial power opera tion), supplementary reports shall be submitted at least every three months until all three events have been completed, i
I f
1 1
10-12 Change No. 46, July 1,1981 Amendment No. 46 T
W