ML20128D725
| ML20128D725 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/29/1993 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20128D710 | List: |
| References | |
| NUDOCS 9302100212 | |
| Download: ML20128D725 (22) | |
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ATTACHMENT-'l' Consumers: Power Company
-Big Rock Point Plant Docket-50-155 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES
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~10 Pages-
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. ADMINISTRATIVE CONTROLS e
l 6.5 REVIEW AND-AUDIT-i 6.5.1 PLANT REVIEW COMMITTEE (PRC) j FUNCTION 6.5.1.1 The Plant Review Committee (PRC) shall function ~ to advise the Plant Manager on all matters-related to nuclear safety.
' COMPOSITION j
6.5.1.2 1he PRC is composed of nine regular members from the: Big Rock Point
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Staff. The PRC members shall meet or exceed the minimum qualifica-
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tions of. ANSI N18.le1971 for comparable positions.
The PRC shall-
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include representatives from the Operations, Chemistry / Health Physics /-
Maintenance and Engineering ~ Departments. ' The' member shall_- be
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designated in administrative procedures-by the Plant Manager who
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is the Chairman of the PRC. The P1 ant Manager shall also designate-
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an Alternate Chairman in writing.
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l-ALTERNATES 6.5.1.3. Alternate members of the PRC shall-be appoir.ted in writing by the i
PRC Chairman to serve on a temporary basis. _However, no more than i-two-alternates shall participate as voting members at any one time-in j.
PRC activities.
l MEETING FRE0VENCY~
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6.5.1.4.The PRC shall meet at least once per calendar month, with.special meetings as required.
i LVORUM l
6.5.1.5 A cuorum for PRC shall consist _of the Chairman or alternate Chairman
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g
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anc ' four1(4)_ voting members (including alternates).-
RESPONSIBILITIES 4
l 6.5.l~.6 The-PRC-shall be~ responsible for:'-
a.
Review of: (1) all' procedures required by Technical;
-Specification 6.8 and changes.thereto and-(2)1any other: proposed-i procedures _or changes thereto:as: determined by the Plant Mhnager-to' affect' nuclear safety.
b. --
Review of all proposed tests and experiments that: affect nuclear safety.
c.
- Review of all proposed changes to AppendixL"A" Technical--
i Specifications.
i R
As Proposed 75 a,_,_.%,_
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s
- @j!NIyTRATIVE CONTROLS i
e RESPONSIBILITIES (Continued)--
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety..
I e.
Investigation of all violations of the Technical 1-Specifications. (A report shall be prepared covering evaluation and recommendations to prevent recurrence and.
forwarded to the Vice President Nuclear Operations and to the Director, Nuclear Performance Assessment ^ Department.)
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f.
Review of plant operations to detect potential nuclear safety hazaras.
{
g.
Review of reportable events a.c defined in Section-l.2.14.
h, Performance of special _ reviews and-investigations and
-reports'thereof~as requested by-the_P1 ant-Manager'or-Nuclear Performance Assessment Department.
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l 1
i.
Review of the Site Emergency Plan-and implementing procedures.
2-j.
Review of any accidental, unplanned-or uncontrolled radioactive release including the. preparation of I
reports covering = evaluation, recommendations and '
disposition of the corrective action to prevent i
recurrence and the forwarding of these reports to-the Plant Manager and to the Director, Nuclear Performance-
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-Assessment Department.
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PRC review may be performed through a routing of'the item subject to the-requirements of Specification 6.5.1.7.
AUTHORITY.
i 6.5.1.7 The PRC shall:
i a.-
Recommend in writing to the Plant _ Manager approval or-4 disapproval' of-items considered _ under Specifications-6 5.1.6.a through d above.-
b.-
Render. determinations in writing with regard to whether or not:each item considered under Specifications 6.5.1.6.a-through e. above constitutes ~an;unreviewed safety question.
76-
-As Proposed-
ADMINISTRATIVE CONTROLS AUTHORITY (Continued) 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 /> to the Vice President - Nuclear Operations and to the Nuclear Performance
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Assessment Department of any disagreement between the PRC
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and the Plant Manager; however, the Plant Manager shall have responsibility for the resolution of such disagreements pursuant to Specification 6.1.1 above.
The PRC Chairman may recommend to the Plant Manager a) proval or
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those items identified in Specifications 6.5.1.6 a, tirough d.
and i, above based on a routing review provided the following conditions are met: (1) at least five PRC members, including the-Chairman and no more than 2 alternates, shall review the item,-
concur with determination as to whether or not the item-constitutes an unreviewed safety question, and provide written comments on the item; (2) all comments shall be resolved to the satisfaction of the reviewers providing the comments; and (3) if the PRC Chairman determines that the comments are significant, the item (including comments and resolutions) shall be recirculated to all reviewers for additional comments.
The item shall be reviewed at a PRC meeting in the event that:
(1) comments are not renlved; or (2) the Plant Manager overrides the recommendations of the PRC; or (3) a proposed change to the Technical Specifications involves a safety limit, a limiting safety system setting or a limiting condition for operation; or (4) the item was a REPORTABLE EVENT as defined in 10 CFR 50.73.
RECORDS 6.5.1.8 The PRC shall maintain written minutes of each PRC meeting and shall provide copies to the NPAD.
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6.5.2 NUCLEAR PERFORMANCE ASSESSMENT DEPARTMENT
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6.5.2.1 FUNCTION The Nuclear Performance Assessment Department (NPAD) shall function /
to provide independent review of activities in the areas of:
a.
Nuclear Power Plant Operation b.
Nuclear Engineering c.
Chemistry and Radiochemistry d.
Metallurgy e.-
Nondestructive Testing f.
Instrumentation and Control 4
g.
Radiological Safety h.
Mechanical and Electrical Engineering i.
Administrative Controls and Quality Assurance Practices J.
Emergency Planning k.
Training 77 As Proposed
.. ~ _ _
ADMINISTRATIVE CONTROLS-1-
I COMPOSITION:
6.5.2.2 The NPAD shall-include ~ the-Director, who reports to. the Vice
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President - N0D, and a full-time staff of Nuclear Performance
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Specialists reporting to-the Director. The Director and the
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Nuclear Performance Specialists shall meett or exceed the
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l qualifications described in Section 4.7 of ANSI /ANS 3.1-1987.
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The NPAD shall have no direct responsibility for activities
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subject to its review.
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CONSULTANTS 6.5.2.3 If sufficient expertise is not available within NPAD for review
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of particular issues, _the NPAD shall have-the authority to utilize
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consultants or other qualified organizations for expert _ advice.
6.5.2.4 RESPONSIBILITIES REVIEW 6.5.2.4.1-NPAD shall review:
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l a.
The safety evaluations'for:' 1) changes to procedures, equipment.or systems,-and 2) tests or experiments completed under the-provi~sions of 10 CFR 50.59 to l
verify that such actions did not constitute:an l_
unreviewed' safety question.
b.
Proposed changes to' procedures, equipment or systems i
which involve an unr.eviewed-safety question;as defined-in 10 CFR 50.59, c.
Proposed tests or experiments which involve _an unreviewed safety question as defined in 10 CFR 50.59.
1
'd.
Proposed changes to Technical Specifications or the Operating-License -
e.
Violations of codes, regulations, orders, Technical Specifications, license. requirements or internal procedures or-instructions having nuclear safety-significance.
f.
Significant, operating abnormalities ~ or deviations from -
normal and expected performance of-plant equipment that-affect nuclear safety.
g.
All REP 0RTABLE EVENTS 'having. nuclear l safety significance.
h.
All recognized indications of an unanticipated deficiency _
in some aspect of design or operation of structures,-
systems or components that could affect nuclear. safety, i.
Reports and meeting minutes of the Plant Review Committee.
~78-As' Proposed.
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AQtilftl11RATIVE CONTROLS AUDITS 6.5.2.4.2 Audits of operational nuclear safety-related facility activities shall be performed by the NPAD Staff under the cognizance of
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Nuclear Performance Specialists.
These audits shall encompasst
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a.
The conformance of plant operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months, b.
The performance, training and qualifications of the entire facility staff at least once per 12 months.
c.
The performance of activities required by the Quality Program Description for 0)erational Nuclear Power
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Plants (CPC-2A) to meet tie criteria of 10 CFR 50, Appendix B, at least once per 24 months, d.
The Site Emergency Plan and implementing procedures at least once per-12 months.:
e.
The Site Security Plan and implementing procedures '(as required by the Site Security Plan) at least once per -
12 months.
f.
Any other area of plant operation considered apr.copriate by MPAD or the Vice. President - Nuclear Operations.-
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g.
The plant Fire Protection Program and implementing procedures at least once per 24 months.
h.
An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm, i.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire censultant at intervals no greater-than 3 years.
J.:
-The Radiological Environmental Monitoring Program and the results thereof at le:st once'per 12 months.
k.
The Offsite Dose Calculation Manual and-implementing procedures at least Once per 24 months.-
79
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As Proposed'
. ~. -
ADMINISTRATIVE CONTROLS i
4 t
6.5.2.4.2(Continued) 1.
The Process Control Program and implementing procedures for processing and packaging of radiokctive wastes at least once per 24 months.
i Audit reports encompassed by 6.5.2.4.2 above shall be forwarded to the Director, NPAD, and management positions
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i responsible for the areas audited within thirty (30) days after completion of the audit.
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l 6.5.2.4.3 NPAD review of the subjects in Specifications 6.5.2.4.1 and
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6.5.2.4.2 shall be performed by an assigned Nuclear Performance
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Specialist selected on the basis of technical expertise
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1 relative to the sub,iect on the basis of technical expertise
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relative to the subject being reviewed, if the assigned
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Nuclear Performance Specialist determines the need for
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j-interdisciplinary review, a committee consisting of the
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s Director, NPAD, or his designate, and at least four Nuclear
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Performance Specialists, shall be assigned.
Such committee
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shall meet as conditions requiring interdisci
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review arise, but no less than twice yearly. plinary
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AUTHORITY 3
6.5.2.5 The NPAD shall report to and advise the Vice President - Nuclear
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Operations of significant findings associated with those: areas of 3
responsibility specified in Section 6.5.2.4.1 and-Section 6.C.2.4.2.
EC.010.li 6.5.2.6 Records of NPAD activities shall be maintained.
Reports shall
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be prepared and distributed as indicated below:
3.
i a.
The results of reviews performed )ursuant to Section-6.5.2.4.1 and Section 6.5.2.4.2 s1all be reported to. the Vice President - Nuclear Operations at least monthly.
b.
A report assessing the overall-' nuclear safety performance of the Big Rock Point Plant shall-be provided to senior Consumers. Power Company management annually, 6.Ji (Deleted) j 6.7 SAFETY' 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-a.
until the Commission authorizes resumption of operation (10CFR50.36(c)(1)(1)(A)).
4 80 As Proposed..
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m-
4 MtiMIMTIVE CONTROLL t
6.7.1 (Continued) b.
The safety limit violation shell be reported within I hour to the Commission in accordance with 10 CFR 50.36, as well as to the Vice President Nuclear Operations and to the NPAD.
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c.
A report shall be prepared in accordance with 10 CFR 50.36 and 6.9 of this s)ecification.
(The safety limit violation and the report shall se reviewed by the PRC.)
d.
The report shall be submitted within 14 days to the Commission (in accordance with the requirements of 10 CFR 50.36), to the Vice President - Nuclear Operations and to the NPAD.
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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 procedures shall meet or exceed the requirements of ANSI N18.7, as endorsed by CPC-2A.
6.8.2 PRC is responsiFJ# for the review of each procedure of 6.8.1 above, and changes thereto (except for Security Im)1ementing Procedures which are reviewed and ap) roved in accordance wit 1 the Site Security Plan).
The Plant Manager siall approve such procedures and changes prior to implementation.
6.8.3 Temporary changes to procedures of 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 designated alternates) of the PRC, at least one of whom holds a Senior Resident Operator's
- License, c.
The change is documented, reviewed by the PRC at the next regularly scheduled meeting and approved by the Plant Manager.
4 h
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81 As Proposed i
@filRISTRATIVE CONTROLS s.9 REPORTING RE0VIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Nuclear Regulatory Commission, Document Control Desk, Washington, DC 20555, with copies to the Regional Administrator and the Resident inspector in accordance with 10 CFR 50.4.
SIMId)P REPORT 4
6.9.1.1 A summary report of plant start-up and power escalation testing shall be submitted following:
(1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant.
6.9.1.2 The start up report shall address each of the tests-identified in the Final Hazards Summary Report and shall include a 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 and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
6.9.1.3 Start up reports shall be submitted within: (1) 90 days following completion of the start-up test p.*ogram, (2) 90 days following resumption or commencement of commercial power o)eration or (3) 9 months following initial criticality, whiciever is earliest.
if the start-up report does not cover all-three events (i.e., initial criticality, completion of start-up test program and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
l 4
82 As Proposed-
ADMINISTRATIVE CONTROLS 6.12.1 (Contd) c.
A radiation protection qualified individual (e.g., Health Physics Technician) with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area, and shall perform periodic radiation surveillance as specified by the Chemistry and Radiation Protection Supervisor in the RWP.
6.12.2 in addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 i
mR/h at 45 cm (18 in.) from the radiation source or from any surface from which the radiation penetrates shall be 3rovided with locked doors to prevent unauthorized entry, and the (eys shall be maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision.
Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area.
In lieu of the-stay time specification of the RWP, direct er remote (such as continuous surveillance may be made by closed circuit TV cameras)iation protection procedures to provide personnel qualified in rad positive exposure control over the activities being performed within the area.
For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.
6.13 ENVIRONMENTAL OVAllFICATION
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(Deleted) 6.14 PROCESS CONTROL PROGRAM (PCP1 6.14.1 Changes to the PCP shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Re) ort for the period in which the change (s) was made effective.
This su)mittal shall contain:
a.
Sufficiently detailed information to support the rationale for the change; t.
A determination that-the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.
Documentation of the fact that the ch nge has been-rnviewed and approved by the responsible Nuclear Operations Department per CPC-2A (Quality Program).
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90 As Proposed
MiiLNISTRATIVE CONTROLS 6,15 OffSITE DOSE CALCULATION MANUAL (ODCH) 6.15.1 Changes to the ODCM shall be submitted to the Commissiu in the Semiannual Radioactive Effluent Release Re) ort for the period in which i
the change (s) was made effective.
This su)mittal shall contain:
a.
Sufficiently detailed information to support the rationale for the change; b.
A determination that the change will not reduce the accuracy 3
or reliability of dose calculations or setpoint determinations; and 1
c.
Documentation of the fact that the change has been reviewed and approved by the responsible Nuclear Operations Department per CPC 2A (Quality Program).
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6.16 RAD _10 ACTIVE MATERIALS SOURCES 4
6.16.1 a.
Each sealed source, except start-up sources subject to core flux, containing byproduct material other than Hydrogen-3, with a half life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months.
In the absence of a certificate from a transferor indicating that a test has been made within six months prior to the transfer, the sealed source shall not be put into use until tested, b.
Notwithstanding the periodic-leak tests required by this condition, any licensed sealed source is exempt from such leak tests when the source contains 100 microcuries or less of beta and/or gamma emitting material.or 10 microcuries or less of alpha emitting material.
c.
lhe periodic leak test required by this condition does not apply to sealed sources that are stored and net being esed. The sources excepted from this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak tested within six months prior to the date of use or transfer.
6.16.2 The test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. The test sample shall be taken from the sealed source or from the surfaces of the device in-which the sealed source is permanently mounted or stored on which one might expect contamination to accumulate.
Records of leak test results shall be kept in units of microcuries and maintained for inspection by the Commission.
91 As Proposed
I ATTACHMENT 2 Consumers Power Company Big Rock Point Plant Docket 50-155 EXISTING TECHNICAL SPECIFICATION PAGES 10 Pages l
@dlN1STRATIVE CONTROLS J
55 REVIEW AND AUDIT
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6.5.1 PLANT REVIEW COMMITTEE (PRC)
FUNCTION i
6.5.1.1 The Plant Review Committee (PRC) shall function to advise the Plant Manager on all matterJ related to nuclear safety, i
COMPOSITION d
6.5.1.2 RC shall be composed of:
p t Chairman:-
t Manager or Designated Alternate inted by the Plan ager 3
Member:
Operations erintendent l
Member:
Maintenance Sup te Member:
En ineering Supe t
l Member:
In trument ontrol.Su isor vember:
-React gineer j-Member:
stry and Health Physics Superi ent Member
- Si.'ift Supervisor.
1 l
. r:-
Technical Engineer ALTERNATES Alternate members of ths. PRC sh'all be appointed in-writing by the-6.5.1.3 i
PRC Chairman to serve on a temporary basis. However, no more than j
two alternates shall participate as voting members at any one-time-in i
PRC activities..
MEETING FRE0VENCY 6.5.1.4 The PRC shall meet at least once-per calendar. month, with special i
meetings as required.
pels OV0 RUM l
6.5.1.5 A quorum for PRC shall consist of the Chairman and four (4)1 voting
- l members (% d%ity).
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l MMINISTRATIVE CONTROLS RESPONSIBillTIES 6.5.1.6 The PRC shall be responsible for:
a.
Review of: (1) all procedures required by Technical Specification 6.8 and changes thereto and 2 any other proposed procedures or changes thereto as determine y the Plant Manager to affect nuclear safety, b.
Review of all proposed tests and experiments that affect l
I nuclear safety.
c.
Review of all proposed changes to Appendix "A" Technical Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety, e.
Investigation of all violations of the Technical Specifications. (A report shall be prepared covering evaluation and recommendations to prevent recurrence and forwarded to the Vice President Nuclear Operations and to the Nuclear Sfi krvic s Department.) Assusmen b t d,a teto g, d o,.i,,, p,< fo c y m a n e e f.
Review of plant operations to detect potential nuclear safety hazards, g.
Review of reportable events as defined in Section 1.2.14.
h.
Performance of special reviews and investigations and reports thereof as requested by the Plant Manager or 4
Nuclear Safety Service: Department.
t
- l'er Cocmo n e.a M s e ss m e nt i.
Review of the Site Emergency Plan and implementing procedures.
j.
Review of any accidental, unplanned or uncontrolled l
radioactive release including the preparation of-reports' covering evaluation, recommendations and disposition of the corrective action to prevent-recurrence and the forwarding of these reports to the Plant Manager and to the Nuclear Safety Services Department. Assessene h bicestor, Nucleae Perhrmane s PRC review may be performed through a routing of the item 'De/4rt rne nt subject to the requirements of Specification 6.5.1.7.
l l
l 76 Amendment 107 February 19, 1992 TSPPNPAD.JLL L
ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The PRC shall:
a.
Recommend in writing to the Plant Manager approval or disapproval of items considered under Specifications 6.5.1.6.a through d. above, b.
Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6.a through e. above constitutes an unreviewed safety question, 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 N'""*""
c.
President - Nuclear Operations and to the Nuclear Gafett d
- U "'/ "
.Saretses Department of any disagreement between the PRC
/
and the Plant Manager; however, the Plant Manager shall
~
have responsibility for the resolution of such disagreements pursuant to Specification 6.1.1 above.
The PRC Chairman may recommend to the Plant Manager a) proval of those items identified in Specifications 6.5.1.6 a. t1 rough d.
and 1. above based on a routing review providcd the following conditions are met: (1) at least five PRC members, including the Chairman and no more than 2 alternates, shall review the item, concur with determination as to whether or not the item constitutes an unreviewed safety question, and provide written comments on the item; (2) all comments shall be resolved to the satisfaction of the reviewers providing the comments; and (3) if the PRC Chairman determines that the comments are significant, the item (including comments and resolutions) shall be recirculated to all reviewers for additional comments.
The item shall be reviewed at a PRC meeting in the event that:
(1) comments are not resolved; or (2) the Plant Manager overrides the recommendations of the PRC; or (3) a proposed change tc the Technical Specifications involves a safety limit, a limiting safety system setting or a limiting condition for operation; or (4) the item was a REPORTABLE EVEdT as defined in 10 CFR 50.73.
RECORDS 6.5.1.8 The PRC shall maintain written minutes of each PRC meeting and shall provide copies to the Scicar-Safety Services Depar4mant,
/
oe NPAb.
77 Amendment 107 February 19, 1992 TSPPNPAD.JLL
o.
ADMINISTRATIVE CONTROLS fa u w m ne.s A sse es m e n t.
6.5.2 NUCLEAR fdf2M SMN426 DEPARTMENT
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FUNCTION I
Pe r %mee.e. 4rse.s s m e A go 6.5.2.1 The Nuclear Wety Servia: Department (1880) shall function
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i-to provide independent review of activities in the areas of:
i j
a.
Nuclear Power Plant Operation 1
1 b.
Nuclear Engineering
{
c.
Chemistry and Radiochemistry d.
Metallurgy i
e.
Nondestructive Testing i
f.
Instrumentation and Control l
g.
Radiological Safety
.j l
h.
Mechanical and Electrical Engineering e
1.
Administrative Controls and Quality Assurance PracAices l
j.
Emergency Planning j
k.'
Training i
COMPOSITION 1
htta.TE 6.5.2.2 h NS!D-thal' ceneic+
a' ' '" " - U -- ' + " i npaiatd by ;d epei 4 4g An n Vice "reMdent-
"" 1 car Oprotleris, i;SO st:ff th!!!' h ": ::
j dimt utpons4b444ty iur edivilia. 59bject2te their rah The NSS9-st-aff shall m et e exceed the.q=1ific ticr,; 4 5cru ed 1
J 4a Sect 4en-4.-7 -cf ANSI /ANS 3.4 - !a*7.
CONSULTANTS-
.NPAb l
l 6.5.2.3 If sufficient expert 1se is not available within $$880 for revf ew of particular-issues, the shall have the authority to utilize l
consultants or other qualifi d organizations-for expert : advice.-
6.5.2.4 RESPONSIBILITIES M
REVIEW NPRb l
6.5.2.4.1 1880 shall review:
I a.
The safety evaluations for:
- 1) changes-to procedures,
)-
equipment or systems, and 2) tests or experiments-completed under the provisions of--10 CFR 50.59 to i
- %e NfRD sha)\\ inc$ ode fl,e $n' rec. tor.j whole PCtks Ao $G Mce frestcle d. Mob dnd a - Coll. tim e sioN o[Oc N S ec$losts re(crt.y To be DirecW. %e-htcuW i.
fer$orma n c e t
ud he %cImeledorna.sei S' recs'aluds sk/l meet n exc. eel L
fh e - 9 veIdi cat onS descc'4 col ik.@ctsor; //. '/ ofANS.E/ANS 1. / -- 1987 7%e. NfAb $)m)} juye no )irgit18 p(ggg;b,),p F [nc ocijv't$ies.
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6.5.2.4.1(Contd) veriff W e such actions did not constitute an unreviewe6 :afety question-b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
c.
Proposed tests or experiments which involve an unreviewed safety question as defined in 10-CFR 50.59.
d.
Proposed changes to Tech:11 cal Specifications or the Operating License, e.
Violations of codes, regulatbns, orders, TecMical Specifications, license requirements or internal procedures or instructions having nuclear safety l
significar,ce, f.
Significant operating abnormalities _or deviations from normal and expected performatice of plant equipment that :
affect nuclear safety.
g.
All. REPORTABLE EVENTS heving nuclear safety significance.
h.
All recognized indications of an unanticipated' deficiency in somi aspect of design or operation of structures, systems or components that could affect nuclear safety.
)-
1.
Repons and meeting ;ninutes of the Plant Review Committee.
AUDITS
%AW7DM 6.5.2.4.2 Auditscfoperationf.nucicarsafety-relatedfacilityactivities j
shall be performed under the cognizance of-N996.
These audits-
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shall-encompass:
- A)mp% P4, g
1 a.
The conformance of plant operation to provisions-contained within the Technical Specifications and -
J applicable license conditions at least once per 12 months.
b.
'The performance, training and qualifications of the.
entire facility staff at least once per 12 months.
/
c; The performance of activities required by the Quality dweveewee-Program Description for Opnrational Nuclecrc Power Plants (CPC 2A) to meet the criteria of-10 CFR 50, Appendix B-at least once per 24_ months..
79' Amendment.107
-February 19,L1992 TSPPNPAD.JLL---
c AGjilfilSlRATIVE10NTROLS 1
6.5.2 4.2 (Contd) d.
The Site Emergency Plan and implementing procedures at least once por 12 months.
M e.
The Site Security Plan and implementing procedures (as required by the Site security Plan) at least once per 1
j 12 months.
f, Any other area of plant operation considered appropriate by M999 or the Vice President - Nuclear Operations.
-/
vmb g.
The plant Fire Protection Program and implementing 4
procedures at least once per 24 months.
h.
An independent fire protection and loss prevention inspection and audit shall be performed annually
. utilizing either qualified offsite licensee personnel or an outside fire protection firm.
1.
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.
j.
The Radiological Environmental Monitoring Progrsm and the results thereof at least once per 12 months.
k.
The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.
1.
The Process Control' Program and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.
hsrect or, Mnh Auditreportsenc[M999,andmanagement'positionsresponsible mpassed by 6.5.2.4.2 above shall= be forwarded to the
/
for the areas audited within thirty (30) days after completion of the audit.
(pnJcoe feckma no e mo N999 review of the subjects in Specifications \\6.5.2.4.1 and
- d 6*
I 6.5.2.4.3
/
6.5.2.4.2-shall be crHed =t by an assigned ind. r;viac selected on the basis of-4 Se technical' expy:;ve-as+=3M to the suoject.being review jed.w ^nd L, review h:ll Mv de " I'"
If the.,_ revi=r er recend 1=1 Sfecob elec be perfer=d.
r:: E _r determines the need for interdisciplinary review,
-Ad* b a "
shall be assigned.
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-Amendment 107 80 February 19, 1992..
TSPPNPAD.JLL
ADMINISTRATIVE CONTROLS s'
s.
AUTil0RITY
- R10 6.5.2.5 The West shall report to and advise the Vice President - Nuclear
/
Operations of significant findings associated with those areas of responsibility specified in Section 6.5.2.4.1 and Section 6.5.2.4.2.
RECORDS
- FAD 6.5.2.6 Records of Neet activities shall be maintained.
Reports shall
/
be prepared and distributed as indicated below:
a.
The results of reviews performed pursuant to Section 6.5.2.4.1 and Section 6.5.2.4.2 shall be reported to the Vice President a Nuclear Operations at least monthly.
b.
A report assessing the overall nuclear safety performance of the Big Rock Point Plant shall be provided to senior Consumers Power Company management annually.
$J.
(Deleted) 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:
a.-
The reactor shall be shut down immediately and not restarted until the Commission authorizes resumption of operation (10 CFR 50.36(c)(1)(1)(A)).
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, as well as to the Vice President - Nuclear Operations and to-the feel Mfao.
/_
c.
A report shall be prepared in accordance with 10 CFR 50.36 and 6.9 of this s)ecification.
(The safety limit violation and the report shall 36 reviewed by the PRC.)
d.
The report shall be submitted within 14 days to the Commission (in accordance with the requirements of 10 CFR 50.36), to the Vice President - Nuclear Operations and.to the JW5h. MPAD,
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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 procedures shall meet or exceed the requirements of ANSI N18.7, as endorsed by CPC-2A.
6.8.2 PRC is responsible for the review of each procedure of 6.8.1 above, and changes thereto (except for Security Implementing' Procedures which are reviewed and apn oved in accordance with the Site. Security Plan),
The Plant Manager sla11 approve such procedures and changes prior to -
implementation.
81 Amendment:107-
-February 19,fl992:
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a
o a'
@MINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 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 designated alternates) of the PRC, at least one of whom holds a Senior Resident Operator's License.
c.
The change is documented, reviewed by the PRC at the next regularly scheduled meeting and approveG by the Plant Manager.
6.9 REPORTING RE0VIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Nuclear Regulatory Commission, r.ccument Control Desk, Washington, DC 20555, with copies to the kegical Administrator and the Resident inApector in accordance with 10 CFR 50.4.
START-UP REPORT 6.9.1.1 A summary report of p1hnt start up and power er,atation totir.g shall be submitted following:
(1) receipt of an ope ^ating license.
(2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufacturedbyadifferentfuelsupplierand(4) modifications that may have significant1.y altered the nuclear, thermal or hydraulic performance of the plant.
6.9.1.2 The start-up report shall address each of the tests identifiw i.i the Final Hazards Summary Paport and shall include a description of the
{
measured values of ths operating conoitions or characteristics obtained during the test program and a comparison of these values with design predictions and 7,pecifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on ether commitments shall be included in this report.
6.9.1.3 Start-up reports shall be submitted within: (1) 90 days following completion of the start-up test pro 5 ram, (2) 90 days following resumption or commencement of commercial power o)eration or (3) 9 months following initial criticality, whiclever is earliest.
If the start up report does not cover all three events (i.e., initial criticality, completion of start-up test program and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every threo moi:ths until all three events have been completed.
82 Amendment 107 February 19, 1992 TSPPNPAD.JLL a
A0filf0STRATIVE CONTROLS 6.12.1 (Contd) c.
A radiation protection qualified individual (e.g., Health Physics Technician) with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within i,
the area, and shall perform periodic radiation surveillance as specified by the Chemistry and Radiation Protection Supervisor in the RWP.
6.12.2 In addition to the iequirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface from which the radiation penetrates sball be )rovided with locked doors to prevent unauthorized entry, and the (eys shall be maintained under the administrative control c1 the Shift Supervisor on duty and/orhealthphysicssupervision.
Doors shall remain locked except during periods of access by personnel under an ap> roved RWP which shall specify the dose rate levels in the immediate wor ( areas and the i
maximum allowable stay timo for individuals in that area.
In lieu of the stay time specification of the RWP, direct or remote (such as continuous surveillance mr.y be made by closed circuit TV cameras)iation protection procedures to provide personnel qualified in r:td positive exposure control over the activities being performed within l
the area.
For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas where no 9nclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.
6.13 ENVIRONMENTAL OVALIFICATION
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(Deleted) 6.14 PROCESS CONTROL PROGRAM (PCP) 6.14.1 Changes to the PCP shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Re) ort for the period in which the change (s) was made effective. This su)mittal shall contain:
a.
Sufficiently detailed information to support the rationale for the change; b.
A determination that the change did not-reduce the'overall conformance of the solidified waste product to existing criteria for solid wastes; and c.
Documentation of the fact that the change has been reviewed and approved by the responsibia Nuclear Operations Department per CPC-2A (Quality Program).
I 90 Auendment 107 February 19, 1992 TSPPNPAD.JLL t
I 6Qtilt((STRATIVE CONTROLS y
s.
I 1
6.15 QEFSITE DOSE CALCULATION MANUAL (0DCM1 i
6.15.1 Changes to the 00CM shall be submitted to the Commission in the Semiannual. Radioactive Effluent Release Re) ort for the period in which
~
j the change (s) was made effective.
This su)mittal shall contain:
I a.
Sufficiently detailed information to support the rationale for the change; j
b.
A determination that the change will not reduce the accuracy 4
or reliability of dose calculations or setpoint l
determinations; and c.
Documentation of the fact that the change has been reviewed l
and approved by the responsible Nuclear Operations _ Department per CPC 2A (Quality Aeewonen Program).
6.16 RADIDACTIVE MATERIALS SOURCES l
6.16.1.a.
Eachsealedsource,exceptstartupsourcessubjectto core flux, containing byproduct material other. than Hydrogen-3, with a half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months.
In the' absence of a i
certificate from a transferor indicating that a test-has been made within six months. prior to the transfer, the sealed source shall not be put into use until tested.
4 b.
Notwithstanding the periodic leak tests required by this condition, any licensed sealed source is exempt from such leak tests when the source contains 100 microcuries or less of beta and/or gamma emitting material or 10 microcuries or less of alpha a
emitting material.
c.
The perindic leak test required by this condition does not apply to sealed sources.that-are stored and not being used. The sources
. excepted from this test shall be tested for leakage prior to any l
use or transfer to another person unless they have been-leak tested within six months prior to the date of use or_ transfer.
6.16.2 The test shall be capable _of. detecting the presence of O.005 microcurie of. radioactive material on the test sample. The.
test sample shall be taken from the sealed source or from the 1
surfaces of the device in which-the sealed source is permanently i
mounted'or. stored on which one might' expect contamination to accumulate.- Records of leak test results shall: be.kept'in units of-microcuries.and maintained for inspection by the Commission.
p i
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l p
91.
Amendment 107 l
February 19, 1992-TSPPNPAD.JLL.
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