ML20151U780
| ML20151U780 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/22/1988 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20151U774 | List: |
| References | |
| NUDOCS 8805020154 | |
| Download: ML20151U780 (9) | |
Text
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3.20 (DELETED)
Acendnent No. 81 3-95a
~8805020154 880422 PDR ADOCK 05000289
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6.
ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Vice President - TMI-1 shall be responsible for unit operations and may, at any time, delegate his responsibili-ties in writing to the Operations and Maintenance Director, TMI-1. He shall delegate the succession of his responsi-bilities in writing during his absence.
6.1.2 The Shift Supervisor (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 President - GPUNC shall be reissued to all unit personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 CORPORATE l'
6.2.1.1 An onsite and offsite organization shall be established for unit operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
- 6. 2.1. 2 Lines of authority, responsibility and communication shall he established and defined from the highest management levels through intermediate levels to and inc1Hing operating organization positions.
These relationships shall be documented and updated as appropriate, in the form of organizational charts. These organizational charts will be documented in the Updated FSAR and updated in accordance with 10 CFR 50.71e.
6.2.1.3 The President-GPUNC shall have corporate responsibility for overall plant nuclear safety and shall take measures to ensure acceptable performance of the staff in operating, maintaining, and providing technical support so that continued nuclear safety is assured.
6.2.2 UNIT STAFF 6.2.2.1 The Vice President-TMI-l shall be responcible for overall unit safe operation and shall have control over those on site activities necessary for safe operation and maintenance of the plant.
6.2.2.2 The unit staff organization shall meet the following:
a.
Each on-duty shift shall be composed of at least the minimum shif t crew composition shown in Table 6.2-1.
b.
At least one licensed Reactor Operator shall be present in the control room when fuel is in the 4
reactor.
6-1 Amendment No, 11, 32, 77
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.s c.
At least two licensed Reactor Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips, d.
The Shift Supervisor or Shift Foreman # shall be in the control room at all times other than cold shutdown conditions (T average < 200*F) when he shall be onsite, e.
An individualff qualified pursuant to 6.3.2 in radiation protection procedures shall be on site when fuel is in the reactor.
f.
A licensed Senior Reactor Operator with no other concurrent operational duties shall directly supervise: (a) irradiated fuel handling and transfer activities on site, and (b) all unirradiated fuel handling and transfer activities to and from the Reactor Yessel.
g.
A Site Fire Brigade ## of at least 5 menbers shall be maintained onsite at all times. The Site Fire Brigade shall not include members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency, h.
The Shift Technical Advisor shall serve in an advisory I
capacity to the Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.
6.2.2.3 Individuals who train the operating staff and those who carry out the health physics and quality assurance function shall have sufficient organizational freedom to be independent from operating pressures, however they may report to the appropriate manager on site.
i i
If not SRO license, he shall have cogleted the SRO Training program.
- The individual of item 6.2.2.2e and the Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided innediate action is taken to fill the required positions.
6-la Amendment No. 11, 32, 77
t I
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI /ANS 3.1 of 1978 for comparable post-tions unless otherwise noted in the Technical Specifications.
Licensed operators shall meet the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.
Individuals who do not meet ANSI /ANS 3.1 of 1978, Section 4.5, are not considered technicians or maintenance personnel for purposes of deter-mining qualifications but are permitted to perform work for which qualification has been demonstrated.
6.3.2 The management position responsible for radiological controls shall meet or exceed the qualifications of Regulatory Guide 1.8 of 1977.
Each radiological controls technician / supervisor shall meet or exceed the qualifications of ANSI-N 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved THI-1 Radiation Controls training program. All radiological controls technicians will be qualified through training and examination in each area or specific task related to their radiological controls functions prior to their performance of those tasks.
6.3.3 The Shift Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in unit design, response and analysis of transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the plant training manager and shall meet or exceed the requirements and recommendations of Regulatory Guide 1.8 of 1977.
Licensed operator training shall also meet the requirements of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1976.
6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL The Vice President of each division within GPU Nuclear Corporation shall be responsible for ensuring the preparation, review, and approval of documents required by the activities described in 6.5.1.1 through 6.5.1.5 within his functional area of responsibility as assigned in the GPUN Review and Approval Matrix.
Irplementing atsrovals shall be performed at the cognizant manager level or above.
6-3 Amendment Nos. 11, 32, 53, 77, 92, 128, 131, 132
ACTiv! TIES
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6.5.1.1 Each procedure required by Technical Specification 6.8 and other procedures which affect nuclear safety, and substantive changes thereto, shall be prepared by a designated individual (s)/ group knowledgeable in the area affected by the procedure.
Each such procedure, and substantive changes thereto, shall be reviewed for adequacy by an individual (s)/ group other than the preparer, but who may be from the same organization as the individual who prepared the procedure or change.
6.5.1.2 Proposed changes to the Appendix "A" Technical Specifications shall be reviewed by a knowledgeable l
individual (s)/ group other than the individual (s) group who prepared the change.
6.5.1.3 Proposed modifications that affect nuclear safety to unit structures, systems and components shall be designed by an individual / organization knowledgeable in the areas affected by the proposed modification.
Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification but may be from the same division as the individual who designed the modification.
- 6. 5.1. 4 Proposed tests and experiments that affect nuclear safety shall be reviewed by a knowledgeable individual (s)/ group other than the preparer but who may be from the same division as the individual who prepared the tests and experiments.
6.5.1.5 Investigation of all violations of the Technical Specifictions including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, shall be reviewed by a knoweldgeable idividual(s)/ group other than the individual / group which performed the investigation.
6.5.1.6 All REPORTABl.E EVENTS shall be reviewed by an individual / group other than the individual / group which prepared the report.
- 6. 5.1. 7 Special reviews, investigations or analyses and reports thereon as requested by the Vice President TMI-1 shall be performed by a knowledgeable individual (s)/ group.
6.5.1.8 The Security Plan and implementing procedures shall be reviewed by a knowledgeable individual (s)/ group other than the individual (s)/ group which prepared them, 6-4 Amendment No. 11, 77, 129 (Use this page if TSCR 177 has been approved)
6.5.1.1 Each procedure required by Technical Specification 6.8 and other procedures including those for tests and experiments which are important to safety, and changes thereto which are important to safety, shall be prepared by a designated individual (s)/ group knowledgeable in the area affected by the procedure.
Each such procedure, and change thereto, shall be reviewed for adequacy by an individual (s)/ group other than the preparer, but who may be from the same organization as the individual who prepared the procedure or change.
6.5.1.2 Proposed changes to the Appendix "A" Technical Specifications shall be reviewed by a knowledgeable individual (s)/ group other than the individual (s) group who prepared the change.
6.5.1.3 Proposed modifications to unit structures, systems and components important to safety shall be designed by an individual / organization knowledgeable in the areas affected by the proposed modification.
Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification but may be from the same division a3 the individual who designed the modification.
6.5.1.4 Proposed tests and experiments that are important to safety shall be reviewed by a knowledgeable individual (s)/ group other than the preparer but who may be from the same division as the individual who prepared the tests and experiments.
- 6. 5.1. 5 nvestigation of all violations of the Technical
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Specifications including the preparation and forwarding of reports covering evaluation and recomendations to prevent recurrence, shall be reviewed by a knowledgeable individual (s)/ group other than the individual / group which performed the investigation.
6.5.1.6 All REPORTABLE EVENTS shall be reviewed by an individual / group other than the individual / group which prepared the report.
- 6. 5.1. 7 Special reviews, investigations or analyses and reports thereon as requested by the Vice President TMI-1 shall be performed by a knowledgeable individual (s)/ group.
6.5.1.8 The Security Plan and iglementing procedures shall be reviewed by a knowledgeable individual (s)/ group other than the individual (s)/ group which prepared them.
6-4 Amendnent No. 11, 77, 129 L
(Use this page if TSCR 177 has not been approved)
6.5.1.9 The Emergency Plan and implementing procedures shall be reviewed by a knowledgeable individual (s)/ group other than the individual (s)/ group which prepared them.
6.5.1.10 A knowledgeable individual (s)/ group shall review every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports to the Vice President THI-1 covering evaluations, recommendations and disposition of the corrective action to prevent recurrence.
6.5.1.11 Major changes to radwaste systems shall be reviewed by a knowledgeable individual (s)/ group other than the individuals (s)/ group which prepared them, 6.5.1.12 Individuals responsible for reviews performed in accordance with 6.5.1.1 through 6.5.1.4 shall include a determination of whether or not additional cross-disciplinary review is necessary.
If deemed necessary, such review shall be performed by the appropriate personnel. Individuals responsible for reviews considered under 6.5.1.1 through 6.5.1.5 shall render determinations in writing with regard to whether or not 6.5.1.1 through 6.5.1.5 constitute an unreviewed safety question.
RECORDS 6.5.1.13 Written records of activities performed under Speciff-cations 6.5.1.1 through 6.5.1.11 shall be maintained.
OllALIFICATIONS 6.5.1.14 Responsible Technical Reviewers shall meet or exceed the qualifications of ANSI /ANS 3.1 of 1978 Section 4.6, or 4.4 for applicable disciplines, or have 7 years of appropriate experience in the field of his specialty. Credit toward experience will be given for advanced degrees on a one-to-one basis up to a maximum of two years.
Responsible Technical Reviewers shall be designated in writing.
6.5.2 INDEPENDENT SAFETY REVIEW FUNCTION 6.5.2.1 The Vice President of each division within GPU Nuclear Corporation shall be responsible for ensuring the periodic independent sa.'ety review of the subjects described in 6.5.2.5 within his assigned area of safety review responsibility, as assigned in the GPUN Review and Approval Matrix.
6.5.2.2 Independent safety review shall be completed by an individual / group not having direct responsibility for the performance of the activities under review, but who may be from the same functionally cognizant organization as the individual / group performing the original work.
6.5.2.3 GPU Nuclear Corporation shall collectively have or have access to the experience and competence required to independently review subjects in the following areas:
Amendme;.t No. 11, 22, 77 6-5
.V dures at least once per 24 nonths.
1.
The Process Control Program and implementing procedures for solidification of radioactive wastes at least once per 24 months, t
j.
The performance of activities required by the Quality Assurance Program to meet criteria of Regt!1atory Guide 4.15, Deceder,1977 at least once per 12 months.
i k.
Any other area of unit operation considered appropriate by the 10SRG or the Office of the President - GPUNC.
6.5.3.2 Audits of the following shall.be performed under the cognizance of the vice president responsible for technical support:
a.
An independent fire protecticn and loss prevention program inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm, b.
An inspection and audit of the fire protection and loss prevention program, by an outside qualified fire consultant at intervals no greater than 3 years.
RECORDS 6.5.3.3 Audit reports encompassed by sections 6.5.3.1 and 6.5.3.2 shall be forwarded for action to the management positions responsible for the areas audited within 60 days after completion of the audit. Upper management shall be informed per the Operation Quality Assurance Plan.
6.5.4 INDEPENDENT ONSITE SAFETY REVIEW GROUP (IOSRG)
STRUCTURE 6.5.4.1 The 10SRG shall be a full-time group of engineers, experienced in nuclear power plant engineering, operations and/or technology, independent of the unit staff, and located on site.
ORGANIZATION 6.5.4.2 a.
The IOSRG shall consist of a manager and a minimum staff of 3 meters who meet the qualifications of l
6.5.4.5.
Group expertise shall be multi-disciplined.
b.
In the event of an unanticipated vacancy in the 10SRG staff, the number of staff can be two (2) mesers for a period of not to exceed six (6) months while the vacancy is being filled, c.
The 10SRG shall report to the director responsible for nuclear safety assessnent.
6-8 Amendment No. 11, 77, 99
s
.s FUNCTION 6.5.4.3 The periodic review functions of the IOSRG shall include the following on a selective and overview basis:
1)
Evaluation for technical adequacy and clarity of procedures important to the safe operation of the unit.
2)
Evaluation of unit operations from a safety perspective.
- 3) Assessment of unit nuclear saft;y programs.
- 4) Assessment of the unit performance regarding conformance to requirements related to safety.
- 5) Any other matter involving safe operations of the nuclear power plant that the onsite IOSRG manager deems appropriate for consideration.
AUTHORITY 6.5.4.4 The 10SRG shall have access to the unit and unit records as necessary to perform its evaluations and assessments.
Based on its reviews, the 10SRG shall provide recommen-dations to the management positions responsible for the areas reviewed.
QUALIFICATIONS 6.5.4.5 The 10SRG engineers shall have either: (1) a Bachelor's Degree in Engineering or the Physical Sciences and three years of professional level experience in the nuclear power field including technical supporting functions, or (2) eight years of appropriate experience in nuclear power plant operations and/or technology. Credit toward experience will be given for advance degrees on a one-to-one basis up to a maximum of two years.
RECORDS 6.5.4.6 Reports of evaluations and assessments encompassed in Section 6.5.4.3 shall be prepared, approved, and transmitted to the director and the division vice president responsible for nuclear safety assessment, the Vice President-TMI-1, and the management positiont responsible for the areas reviewed.
6-9 Amendment No. 11, 77, 99, 132
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