ML20066E169
| ML20066E169 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 10/29/1982 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20066E163 | List: |
| References | |
| NUDOCS 8211120459 | |
| Download: ML20066E169 (12) | |
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APPENDIX H DRAFT MIDLAND TECHNICAL SPECIFICATIONS Rev 1 8211120459 821103 PDR ADOCK 05000329 A
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ADMINISTRATIVE CONTROLS 16.6.1 RESPONSIBILITY 16.6.1.1 The Plant General Manager shall be responsible for overall plant opera-tion and shall delegate in writing the succession to this responsibility during his absence.
16.6.1.2 The Shift Sup.ervisor (or during his absence from the control room, a designated individual) shall be responsible for the control room command function.
A Management directive to this effect, signed by the Vice President - Nuclear Gperations, shall be reissued to all station personnel on an annual basis.
16.6.2 ORGANIZATION OFFSITE 16.6.2.1 The offsite or'ganization for plant management and technical support shall be as shown in Figure 16.6.2-1.
PLANT STAFF 16.6.2.2 The plant organization shall be as shown in Figure 16.6.2-2 and:
a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 16.6.2-1.
b.
At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor.
In addition, while either unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the control room.
c.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.*
d.
All CORE ALTERATIONS, after the initial fuel loading, shall either be performed by a licensed deactor Operator under the general super-vision of a Senior Reactor Operator or a nonlicensed operator di-rectly supervised by a licensed Senior Reactor Operator (or Senior Operator Limited to Fuel Handling) who has no other concurrent re-sponsibilities during this operation.
e.
A Fire Brigade of at least 5 members shall be maintained on site at all times.* The Fire Brigade shall neither include 3 members of the minimum shift crew necessary for safe shutdown of the unit nor any i
- Radiation protection coverage and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed two hours in order to accommodate unexpected absence provided immediate action is taken to restore the minimum requirements, nul082-0507a-43-48 16.6-1 PROPOSED /MID 10-29-82 Y
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J ADMINISTRATIVE CONTROLS personnel required for other essential functions during a fire emergency.
16.6.2.3 NUCLEAR ACTIVITIES PLANT ORGANIZATION (NAPO)
FUNCTION 16.6.2.3.1 The NAPO shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources which gay indicate areas for improving plant safety. The organization shall report to the Execut'ive Engineer - NAPO. With the concurrence of the Executive Engineer, NAPO may function as staff to the onsite and offsite review organizations and provide technical support for problem resolution and General Office interface.
COMPOSITION 16.6.2.3.2 The NAPO shall be composed of members located at other Consumers Power Company facilities, and onsite members at the Midland Plant. The NAPO on site shall consist of a minimum of five (5) technical personnel.
QUALIFICATIONS 16.6.2.3.3 Three of the full-time members shall each have a bachelor's degree in engineering, or a related science. One of the three shall have a minimum of five years professional experience which includes a minimum of two years experience in power plant operation and/or design.
Any NAPO member may be drawn upon to perform NAPO duties on a temporary basis at any nuclear plant location.
16.6.2.3.4 REPORTS
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Regular reports of NAPO activities shall be submitted to the NSB.
16.6.2.4 SHIFT ENGINEER The Shift Engineer shall serve in an advisory capacity to the Plant Supervisor on i
matters pertaining to the engineering aspects assuring safe operation of the unit.
t 16.6.3 PLANT STAFF QUALIFICATIONS l
16.6.3.1 Each member of the plant staff shall meet or exceed the minimum quali-fications of ANSI N18.1-1971 for comparable positions and the supplemental re-quirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC
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Nl ADMINISTRATIVE CONTROLS 16.6.3.2 The functions of the Radiation Protection Manager (CRPM) specified in Regulatory Guide 8.8, March 1979, shall be accomplished by an individual (or individuals) who meets or exceeds the qualifications of Regulatory Guide 1.8, May 1977.3 These functions shall be carried out by either the Chemistry / Health Physics Superintendent or by a qualified individual (or individuals) who reports to him.
16.6.3.3,The Shift Engineer shall have a. bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and/or operations and response and analysis of the plant for transients and accidents.
16.6.4 TRAINING 16.6.4.1 A retraining and replacement training program for the plant staff shall be maintained under the direction of the Director of Nuclear Operations Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971, 10 CFR 55, Appendix "A," and the ' supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter, and shall include familiarization with relevant industry operational experience.
16.6.4.2 The Director of Property Protection is responsible for the development, revision, approval and implementation of the Fire Brigade training program. This training shall, as practicable, meet or exceed the requirements of Section 27 of the NFPA Code-1975.
Fire Brigade. training drills shall be held at least quarterly.
16.6.5 REVIEW AND AUDIT 16.6.5.1 PLANT REVIEW COMMITTEE (PRC)
FUNCTION 16.6.5.1.1 The Plant Review Committee (PRC) shall function to advise the Plant General Manager on all matters related to nuclear safety and to provide an examination of plant operating data.
'For the purpose of this section, " Equivalent," as utilized in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following:
(a) Formal schooling in science or engineering, or (b) operational or technical experience / training in nuclear power.
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al ADMINISTRATIVE CONTROLS COMPOSITION 16.6.5.1.2 The PRC shall be composed of:
Chairman: Technical Engineer or Alternate Appointed by the Plant General Manager Member:
Plant Superintendent Member:
Operations Superintendent Member:
Technical Superintendent Member:
Maintenance Superintendent Member:
Chemistry / Health Physics Superintendent Member:
Reactor Engineer Member:
Senior Engineer Member:
Plant / Shift Supervisor or Shift Engineer
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ALTERNATES 16.6.5.1.3 Alternate members of the PRC shall be appointed in writing by the PRC Chairman to serve on a temporary basis. However, no more than two alternates shall participate as voting members at any one time in PRC activities.
3 MEETING FREQUENCY 16.6.5.1.4 The PRC shall meet at least once per calendar month, with special meetings as required.
QUORUM 16.6.5.1.5 A quorum for PRC shall consist of the Chairman and four (4) voting members.
~1 RESPONSIBILITIES 16.6.5.1.6 The PRC shall be responsible for:
a.
Review of:
(1) all procedures required by Specification 16.6.8.2 and changes thereto, (2) all programs required.by Specifica-tion 16.6.8.4 and changes thereto and (3) any other proposed pro-cedures or changes thereto as determined by the PRC Chairman to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety and changes to procedures as described in the Final Safety Analysis Report,
. Review of all proposed changes to Appendix "A" Technical Specifi-c.
catio.ns.
d.
Review of all proposed clyanges or modifications to plant, systems or equipment that affect nuclear safety.
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ADMINISTRATIVE CONTROLS e.
Investigation of all violations of the Technical Specifications.
(A report shall be prepared covering evaluation and recommenda-tions to prevent recurrence and forwarded to the Vice President -
Heclear Operations and to the Executive Engineer - NAPO.)
f.
Review of events requiring 24-hour written notification to the Commission.
g.
Performance of special reviews and investigations and reports thereof as requested by the Plant General Manager or Chairman of NSB.
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Review of the Site Emergency Plan.
- i. Review of each unplanned release reportable under Specifica-tion 16.6.9.1.12 of radioactive material to the environs exceeding 25% of 10 CFR 50, Appendix "B" concentration for air and water or exceeding Appendix "C" quantities for solid materials, including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action.
J.
Review of major changes to radwaste treatment systems.
AUTHORITY 16.6.5.1.7 Authority of PRC is as follows:
a.
The PRC shall:
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(1) Recommend in writing to the Plant General Manager approval or disapproval of items considered under Specifica-tions 16.6.5.1.6.a. through d. above.
(ii) Render determinations in writing with regard to whether or not each item considered under Specifications 16.6.5.1.6.b.
and d. above constitutes an unreviewed safety question.
(iii) Render determinations in writing with respect to the impact on safety of each item considered under Specifica-tions 16.6.5.1.6.a., c. and e.
b.
The PRC Chairman shall:
(1)' 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 Vice Chairman of
, NSB of any disagreement between the PRC and the Plant Ger ral Manager; however, the Plant General Manager shall he e responsibility for the resolution of such disagree-ments pursuant to Specification 16.6.1.1 above.
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c.
PRC may delegate activities associated with fulfilling its responsibilities under Specification 16.6.5.1.6.
Those activities specified in Specifications 16.6.5.1.7.a and b. above, however, may not be delegated.
RECORDS 16.6.5.1.8 The PRC shall maintain written minutes of each PRC meeting and shall I
maintain records of transactions specified in. Specifications 16.6.5.1.6.b. and c.
16.6.5.2 NUCLEAR SAFETY BOARD (NSB)
RESPONSIBILITIES 16.6.5.2.1 The Nuclear Safety Board (NSB) is responsible for maintaining a continuing examination of nuclear safety-related corporate and plant activities and defining opportunities for policy changes related to improved nuclear safety performance.
FUNCTION 16.6.5.2.2 The NSB shall function to provide review of designated activities in the areas specified in Specification 16.6.5.2.3.
COMPOSITION 16.6.5.2.3 The NSB shall consist of members appointed by the Vice President -
Suclear Operations.
NSB shall'be chaired by the Executive Director, Nuclear Activities, the Vice Chairman, or a duly appointed alternate. The Executive Engineer - NAPO shall be the Vice Chairman and Secretary.
Collectively, the personnel appointed to NSB shall be competent to conduct reviews in the following areas:
a.
Nuclear Power Plant Operations b.
Nuclear Engineering c.
Chemistry and Radiochemistry d.
Metallurgy i
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Instrumentation and Control f.
Radiological Safety e
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Mechanical and Electrical Engineering I
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Quality Assurance Practices l
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An individual appointed to NSB may possess expertise in more than one of the above f
specialties. These individuals should, in general, have had professional experi-snce in their specialty at or above the Senior Engineer level.
b AUTERNATE HEMBERS 16.6.5.2.4 Alternate members may be appointed in writing by the Vice President -
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Nuclear Operations to act in place of members during any legitimate and unavoid-cble absences. The qualifications of alternate members shall be similar to those of members.
CONSULTANTS 16.6.5.2.5 Consultants shall be utilized as determined by the NSB Chairman or Vice Chairman to provide expert advice to the NSB. NSB members are not restricted as to sources of technical input and may call for separate investigation from any competent source.
MEETING FREQUENCY 16.6.5.2.6 NSB shall meet at least once per calendar quarter ~during the initial year of facility operation following fuel loading and at least once every six months thereafter.
QUORUM 16.6.5.2.7 A quorum of NSB shall consist of the Chairman and four (4) members.
(The Vice Chairman may be a voting member when not acting in the capacity of Chairman.) No more than a minority of the quorum shall have line responsibility for operation of the facility.
It is the responsibility of the Chairman to ensure that the quorum convened for a meeting contains appropriately qualified members or has at its disposal consultants sufficient to carry out.the review functions re-quired by the meeting agenda.
16.6.5.2.8 RESPONSIBILITIES REVIEW 16.6.5.2.8.1 NSB shall be responsible for the review of:
Significant operating abnormalities or deviations from normal a.
and expected performance of plant equipment that affect nuclear safety.
b.
All events which are required by regulations or Technical Speci-fications to be reported to NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and other violations (of applicabic statutes, codes, regulations, orders, Technical Specifications, licens'c requirements or of internal procedures 6r instructions) having nuclear safety significance.
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' Issues of safety significance identified by the Plant Manager, c.
the NSB Chairman, Executive Engineer, NAPO or the PRC.
d.
Proposed changes in the operating license or Appendix "A"
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Technical Specifications.
The results of actions taken to correct deficiencies identified e.
by the audit program specified in Specification 16.6.5.2.8.2 at least once every six months.
f.
Safety evaluations "or changes, completed under the pro' visions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question.
AUDITS 16.6.5.2.8.2 Audits of operational ~ nuclear safety-related facility activities shall be performed under the cognizance of NSB. These audits shall encompass:
The conformance of. plant operation to provisions contained a.
within the Technical Specifications and applicable license conditions at.least once per 12 months.
b.
The performance, training and qualificat' ions of the entire facility staff at least once per 12 months.
The performance of activities required by the operational c.
quality assurance program (CPC-2A QAPD) to meet the criteria of Appendix "B," 10 CFR 50, at least once per 24 months.
d.
The Site Emergency Plan and implementing procedures at least once per 12 months.
The Site Security Plan and implementing procedures (as required e.
by the Site Security Plan) at least once per 24 months.
f.
Any other area of plant operation considered appropriate by NSB or the Vice President - Nuclear Operations.
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 qualifed fire consultant at intervals no greater than 3 years.
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- j. The radiological environmental monitoring program 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 solidification of radioactive wastes at least on.ce per 24 months.
Audit reports encompassed by Specification 16.6.5.2.8.2 above shall be forwarded to the NSB Vice Chairman and Secretary and Management positions responsible for the areas audited within thirty (30) days after completion of the audit.
AUTHORITY 16.6.5.2.9 Authority of NSB is as follows:
a.
For responsibilities specified in Specifications 16.6.5.2.4.1.a.
and b., the NSB shall be convened.
In making determinations and recommendations, the.NSB may utilize reviews cpnducted by NAPO.
b.
The NSB Chairman shall report to and advise the Vice President -
Nuclear Operations of'significant findings associated with NSB activities and of recommendations related to improving plant nuclear safety performance.
NSB may delegate activities associated with fulfilling its c.
responsibilities under Specification 16'. 6. 5. 2. 8.
Those activities specified in Specification 16.6.5.2.9.a. above, however, may not be delegated.
RECORDS 16.6.5.2.10 Records of 3B activities shall be prepared and distributed as indi-cated below:
a.
Minutes of each NSB meeting shall be prepared and forwarded to the Vice President - Nuc1 car Operations and each NSB member. Minutes shall be approved at or before the next regularly scheduled meeting following the distribution of the minutes.
b.
If not included in NSB meeting minutes, reports of reviews encom-passed by Specification 16.6.5.2.8.1 above shall be prepared and i
forwarded to the Vice President - Nuclear Operations.
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S k?.$q Q Y ji ADMINISTRATIVE CONTROLS 16.6.7 SAFETY LIMIT VIOLATION 16.6.7.1 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 a.
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 Chairman - NSB.
A report shall be prepared in accordance with 10 CFR 50.36 and c.
Specification 16.6.9'of this specification.
(The safety limit violation and the report shall be 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 Chairman - NSB.
16.6.8 PROCEDURES AND PROGRAMS 16.6.8.1 Written procedures shall be established, implemented and maintained cov-ering the activities referenced below:
The applicable safety-related procedures recommended in Appendix "A" a.
of Regulatory Guide 1.33, Quality Assurance Program Requirements, as endorsed by CPC-2A QAPD.
b.
Refueling operations.
c.
Surveillance and test activities of safety-related equipment.
d.
Site Security Plan implementation.
Site Emergency Plan implementation.
e.
f.
Site Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation.
- i. Conduct of a program of interlaboratory comparison of radiological analyses.
16.6.8.2 PRC is responsible for the review of each procedure of Specifica-tion 16.6.8.1 above and changes thereto (except for Security Implementing Proce-dures which are reviewed and approved in accordance with the Site Security Plan).
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The Plant General Manager shall approve such procedures and changes prior to implementation.
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t 16.6.8.3 Temporary changes to procedures of Specification 16.6.8.1 above may be sade provided:
i a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one o'f whom holds a Senior Reactor Operator's License on the unit affected.
Thechangeisdocumented,consideredbytl$ePRCatthenextregu-c.
larly scheduled meeting, and subsequently approved by the Plant Manager.
16.6.8.4 The following programs shall be established, implemented and maintained:
a.
Primary Coolant Sources outside Containment A program to reduce leakage from those portions of systems outside' containment that could contain highly radioactive fluids during a j
serious transient or accident to as low as reasonably achievable j
levels. The systems: include the reactor building spray and safety i
injection system. The program shall include the following:
l (1) Preventive maintenance and periodic visual inspection requirements, and I
{ii)
Integrated leak test requirements for each system at t
intervals not exceeding the refueling cycle.
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b.
In-Plant Radiation Monitoring A program which will ensure the capability to determine accurately the airborne iodine concentration in occupied areas under accident conditions. This program shall include the following:
l (i) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.
l c.
Secondary Water Chemistry A program for maintenance of secondary water chemistry to inhibit steam generator tubo degradation. This program shall include:
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