ML20150D269
| ML20150D269 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/17/1988 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20150D265 | List: |
| References | |
| NUDOCS 8803230274 | |
| Download: ML20150D269 (11) | |
Text
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TABLE OF CONTENTS Section Page 1
3,16 SH0CK SUPPRESSORS (SNUBBERS) 3-63 3.17 REACTOR BUILDING AIR TEMPERATURE 3-80 3.18 FIRE PROTECTION 3-86 3.18.1 FIRE DETECTION INSTRUMENTATION 3-86 3.18.2 FIRE SUPPRESSION WATER SYSTEM 3-88 3.18.3 DELUGE / SPRINKLER SYSTEMS 3-89 3.18.4 CO2 SYSTEM 3-90 3.18.5 HALON SYSTEMS 3-91 3.18.6 FIRE HOSE STATIONS 3-92 3.18.7 FIRE BARRIER PENETRATION SEALS 3-94 3.19 CONTAINMENT SYSTEMS 3-95 3.20 DELETED 3-95a 3.21 RADI0 ACTIVE EFFLUENT INSTRUMENTATION 3-96 3.21.1 RAUI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION 3-96 3.21.2 RADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT 3-100 MONITORING INSTRUMENTATION 3.22 RADIOACTIVE EFFLUENTS 3-106 3.22.1 LIQUID EFFLUENTS 3-106 3.22.2 GASEOUS EFFLUENTS 3-111 3.22.3 SOLID RADIOACTIVE WASTE 3-118 3.22.4 TOTAL DOSE 3-119 3.23 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-120 3.23.1 MONITORING PROGRAM 3-120 3.23.2 LAND USE CENSUS 3-125 3.23.3 INTERLABORATORY COMPARISON PROGRAM 3-127 4
SURVEILLANCE STANDARDS 4-1 4.1 OPERATIONAL SAFETY REVIEW 4-1 4.2 REACTOR COOLANT SYSTEM INSERVICE INSPECTION 4-11 4.3 TESTING FOLLOWING OPENING OF SYSTEM 4-28 4.4 REACTOR BUILDING 4-29 4.4.1 CONTAINMENT LEAKAGE TESTS 4-29 4.4.2 STRUCTURAL INTEGRITY 4-35 4.4.3 DELETED 4-37 4.5 EMERGENCY LOADING SEQUENCE AND POWER TRANSFER, 4-39 i
EMERGENCY CORE COOLING SYSTEM AND REACTOR I
BUILDING COOLING SYSTEM PERIODIC TESTING 4.5.1 EMERGENCY LOADING SEQUENCE 4-39 4.5.2 EMERGENCY CORE COOLING SYSTEM 4-41 4.5.3 REACTOR BUILDING COOLING AND ISOLATION SYSTEM 4-43 4.5.4 DECAY HEAT REMOYAL SYSTEM LEAKAGE 4-45 4.6 EMERGENCY POWER SYSTEM PERIODIC TESTS 4-46 4.7 REACTOR CONTROL ROD SYSTEM TESTS 4-48 4.7.1 CONTROL ROD DRIVE SYSTEM FUNCTIONAL TESTS 4-48 4.7.2 CONTROL ROD PROGRAM YERIFICATION 4-50
-111-Amendmen t 72, 81, 108, 129 s
N 8803230274 880317 PDR ADOCK 05000289 P
4 LIST OF FIGURES Figure Title 3.5-2K Power imbalance Envelope for Operation after 30+10/-0 EFPD, THI-l 3.5-2L LOCA Limited Maximum Allowable Linear Heat Rate 3.5-1 Incore Instrumentation Specification Axial Imbalance Indication, THI-l 3.5-2 Incore Instrumentation Specification Radial Flux Tilt Indication,T MI-l 3.5-3 Incore Instrumentation Specification 3.11-1 Transfer Path to and from Cask Loading Pit 4.17-1 Snubber Functional Test - Sample Plan 2 5-1 Extended Plot Plan TMI 5-2 Site Topography 5 Mile Radius 5-3 Site Boundary for Gaseous Effluents 5-4 Site Boundary for Liquid Effluents l
i viii Amendnen t Nos.' 72, 77, 126
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3.20 (DELETED)
Amendment No. 81 3-95a
l 6.
ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY -
i 6.1.1 - The Vice President - THI-1 shall be responsible for unit i
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-a bilities in writing during his ' absence.
J 6.1.2 The Shift Supervisor (or during his absence from the Control Room, a designated individual), shall be responsible for the i
Centrol-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 6.2.1.1 An onsite and offsite. organization shall 1e. 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 consunication shall be established and defined from the highest managemtnt levels through intermediate levels to and including operating organization positions. These relationships shall be documented and updated as
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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 There shall be an individual executive pos'. tion having corporate responsibility for measures needed to ensure acceptable performanc? 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 There shall be an individual management position in the onsite organization having responsibility for overall unit operation and shall have control over those resources 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 compositd of at least the minimum shift crew compositiion shotin in Table 6.2-1.
b.
At least one licensed Reactor Operator shall be present in the control room when fitel is in the reactor.
6-1 Amendment No. 11, 32, 77
I, 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 individual ## 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 Vessel, g.
A Site Fire Brigade ## of at least 5 members 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 capacity to the Shift Supervisor on matters pertaining to the engineering aspect: 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.
- If not SR0 license, he shall have completed the SR0 Training program.
- The individual of item 6.2.2.2e and the Fire Brigade composition l
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 immediate action is taken to fill the required positions.
6-la Anendment No. 11, 32, 77
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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, 1580 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 TMI-l 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 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.
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i 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-i as assigned in the GPUN Review and Approval Matrix.
Implementing approvals shall be performed at the cognizant manager level or above.
6-3 Amendment Nos. 11, 32, 53, 77, 92, 128, 131, 132
4 ACTIVITIES 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 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 tnan 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 THI-1 shall be performed by a knowledgeable individual (s)/grcup.
6.5.1.8 The Security Plan and implementing procedures shall be reviewed by a kncwledgeable individual (s)/ group other than the individual (s)/ group which prepared them.
6-4 Amendnent No. 11, 77, 129 (USE THIS PAGE IF TSCR 177 HAS BEEN APPROVED)
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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 knowledgeablo 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 as 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 Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, shall be reviewed by a knowledgeable 1
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.
l 6.5.1.7 Special reviews, investigations or analyses and reports thereon as requested by the Vice President THI-l shall be performed by a knowledgeable individual (s)/ group.
6.3.1.8 The Security Plan and im)lementing procedures shall be reviewed by a knowledgea)1e 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 NOT BEEN APPROVED)
i
-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 i
environs including the preparation and forwarding of reports to the Vice President THI-1 covering evaluations, I
recommendations and disposition of the corrective act.fon i
to prevent recurrence.
l 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 acccrdance 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 perfomed under Speciff-cations 6.E,1.1 through 6.5.1.11 shall be maintained.
QUALIFICATIONS 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 safety 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 perfomance 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 Corport. tion shall collectively have or have access to the experience and competence required to independently review subjects in the following areas:
Amendment No. 11, 22, 77 6-5
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dures at least once per 24 months,
- i. The Process Control Program and inplementing procedures for solidification of radioactive wastes at least once per 24 months.
J.
The performance of activities required by the Quality Assurance Program to meet criteria of Regulatory Guide 4.15, December,1977 at least once per 12 months.
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 protection 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 Ouality 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 10SRG shall consist of a manager and a minimum staff of 3 members who meet the qualifications of 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) menbers for a period of not to exceed six (6) months while the vacancy is being filled, c.
The 10SRG shall report to a Director level position in the assigned GPUN Division.
6-8 Amendment No. 11, 77, 99
r 2
FUNCTION 6.5.4.3 The periodic review functions of the 10SRG 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 c safety i
perspective.
- 3) Assessment of unit nuclear safety 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 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 IOSRG 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 IOSRG Division management, and the management positions responsible for the areas reviewed.
6-9 Anendment No. 11, 77, 99, 132
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