ML19325C636
| ML19325C636 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/11/1989 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML19325C634 | List: |
| References | |
| NUDOCS 8910170122 | |
| Download: ML19325C636 (24) | |
Text
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OYSTER CREEK NUCLEAR GF.NERATING STATION h
PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 167, Rev. 1 1.
Sections to be chanced a.
Section 6 - all pages.
2.
Extent of Chanoes a.
Organization charts on pages 6-3, 6-4 and 6-5 are deleted.
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Section 6.2: Deleted organisation charts; delineated corporate l
responsibility for overall plant nuclear safety to President - GPUN; and delineated responsibility for onsite activities necessary for L-safe operation and maintenance of the plant to Vice President &
Director, Oyster Creek.
c.
Section 6.3: Deleted plant specific titles and referenced ANSI /ANS 3.1 of 1978 to specify minimum qualifications for comparable positions.
Incorporated the qualifications for the shif t technical advisor into Section 6.3.3.
d.
Section 6.48 Revised to reflect revised 10 CFR Part 55 and substituted a comparable title responsible for training of the licensed operators and Fire Brigade.
e.
Sections 6.5.1 and 6.5.2.1:
Revised to reflect deletion of the organization charts.
f.
Section 6.5.3.1:
Revised to reflect an organizational change and substituted a comparable title.
g.
Section 6.5.3.2:
Substituted a comparable title for the GPUN title of Vice President - Technical Functions.
h.
Section 6.5.4 Substituted comparable titles for GPUN titles.
- i. Section 6.9.3:
Revised location to which reports are sent.
3 Section 6.13.1:
Substituted a comparable title for the CPUN title.
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Sectien 6.19a: Corrected tipographical arror.
1.
Pages 6-2, 6-4, 6-6, 6-12, 6-14, 6-15, and 6-18 retyped - no changes other than revised page numbers where required.
3.
Chances Recuested P
Replace page 111 and entire Section 6 with the new pages attached. 6967f l
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Reason for Changg 3
10 CPR 50.36 delineates the regulatory requirements for including administrative controle in the TS.
This regulation defines administrative controls as those provisions relating to the organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
By GL 88-06, the NRC staff has concluded that organization charts by j
thommelves do not ensure compliance to the administrative controle
. I requirements of 10 CFR 50.36.
Specific requirements are already specified elsewhere in the plant specific TS which bear more directly on i
operational safety and management functions.
For Oyster Creek, the control room command function as well as the requirements for minimum staf fing are already specified in 6.2.2.
Further, the management functions for technical review (TS 6.5.1),
i independent safety review (TS 6.5.2), audits (TS 6.5.3), and independent onsite review group (TS 6.5.4) are also specified in the DC TS.
Based on these facts, the removal of the organization charts from the DC TS are administrative in nature and do not change the administrative controls i
which are required by 10 CFR 50.36.
The organization charts are included in Chapter 13 of Update Number 3 to the Updated FSAR, issued May 27, j
1988.
Future changes to the organization will be included with the annual updates in accordance with 10 CFR 50.71.
Besides the deletion of the organization charts, other changes are proposed in this TSCR.
Facility staff qualifications (6.3.1) except for the Shift Technical Advisor are replaced with a commitment to ANSI /ANS
.3.1 of 1978 for comparable positions. An exception is taken to Section i
4.5 of ANSI /ANS 3.1 of 1978 to allow the award of technician and maintenance positions to individuals who demonstrate qualifications to existing Oyster Creek job descriptions. Position titles are made generic where deemed appropriate, and references to deleted figures are removed.
5.
Safety Evaluation Justifyino chance The deletion of the organization charts, from the Technical Specifications does not have an adverse effect on safety. Although this item no longer will be detailed in the Technical Specifications, the details are included by Update Number 3 to the Updated FSAR.
Replacement of the specified facility staff qualifications with a p
commitment to an NRC accepted standard that delineates the minimum qualifications for comparable positions, is an option made available to i
the licensee.
Since thu minimum qualifications for facility staff personnel including the technicians and maintenance personnel are not changed, there is no adverse effect on safety.
l The remaining items in this TSCR are administrative in nature and do not have an effect on safety. These items include replacing GPUN titles with generic titles and correcting typographical errors. 6967f 1
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sianificant Hamards canaideration i
i This proposed changs is similar to'estaple (i) of the ' Amendments Not Likely to Involve Significant Hazards Consideration" from the Federal Register Vol. 48, No. 67 at 14870 on April 6, 1983.
j This change is considered an administrative change. This Technical Specification Change Request does not involve significe.nt hasards consideration as stated below.
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(1) Involve a significant increase in the probability or consequences of an accident previously evaluated.
The propoued change does not involve a significant increase in the l
probability or consequences of an accident previously evaluated i
because deletion of the organisation charts, and position titles 1
from the Technical Specificatione does not affect plant operation.
As in the past, the NRC will continue to be informed of j
organizational changes through other required controls.
In accordance with 10 CFR 50.34 (b)(()(1) the applicant's j
organizational structure is required to be included in the Updated r
Final Safety Analysis Report. Chapter 13 of the Updated Final Safety Analysis Report provides a description of the organiaction and detailed organization charts.
As required by 10 CFR 50.71 (e) OPUN submits annual updates to the l
Updated FSAR. Appendix B to 10 CFR Part 50 and 10 CFR 50.54 (a)(3) govern changes to organisation described in the Quality Assurance Program. Some of these organizational changes require prior NRC approval. Also, it is CPUN's practice to inform the NRC of organizational changes affecting the nuclear facilities prior to implementation.
(2) Create too possibility of a new or different kind of accident from any accident previously evaluated.
I The proposed amendment does not create the possibility of a new or
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different k!nd of accident than previously evaluated because the proposed change is administrative in naturo, and no physical alterations of plant configuration or changes to setpoints ur operating parameters are proposed.
(3) Involve a significant reduction in a margin of safety.
3 The proposed amendment dose not involve a r*gnificant reduction in a wargin of safety because CPUN, through its Quality Assurance program committed, to maintain qualified personnel in positions of responsibility.
Therefore, removal of the organisation charts and plant specific personnel qualifications from the Technical Specifications will not affect the margin of safety.
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Implementation 7
i It 'is requested that the ' amendment authorising this change becow l
effective 60 days after issuance.
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1-nd=nt Fee (10CFRT70.211 1
Purnuant to the provisions of 10CFR170.21, a check for $150.00 was included with GPUN letter dated March 22, 1988.
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TABLE OF CONTENTS (Cont'd) c' Section 5 Design Features 5.1 Site 5.1-1 5.2 containment 5.2-1 f
5.3 Auxiliary Equipment 5.3-1 I
section 6 Administrative controls 6.1 Responsibility 6-1 i
6.2-
'Organisation 6-1 6.3 Facility Staff Qualifications 6-2a 6.4 Training 6-3 6.5 Review and Audit 6-3 6.6 Reportable Event Action 6-9 6.7 Safety Limit Violation 6-9 6.8 Procedures 6-10 6.9 Reporting Requirements 6-10 i
6.10 Record Retention 6-14 5
6.11 Radiation Protection Program 6-15 6.12 (Deleted) 6-15 6.13 High Radiation Area 6-15 6.14 Environmental Qualification 6-16*
6.15 Integrity of systems Outside Containment 6-16 6.16 Iodine Monitoring 6-16 6.17 Post Acciden*. Sampling 6-17 6.18 Process Control Plan 6-17 6.19
-Offsite Done Calculation Manual 6-17 6.20 Major Changes to Radioactive Waste Treatment Systems 6-18 i
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- Issued by NRC Order dated 10-24-80 f
OYSTER CREEK iii Amendment No.: 84, 97, 98, 108, 115 i
f ao ADMINISTRATIVE OONTROLS 6.1 KESPONSIBILITY 6.1.1 The Vice President & Director Oyster Creek shall be responsible for overall facility operation. Those responsibilities delegated to the Vice President & Director as stated in the Oyster Creek Technical Specifications may niso be fulfilled by the Deputy Director. The Vice President & Director shall delegate in writing the succession to this responsibility during his and/or the Deputy Directors absence.
.j 6.2 ORGANIEATION 6.2.1 Coroorate 6.2.1.1 An onsite and offsite organisation shall be established for unit operation and corporate management. The onsite and offsite organisation 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 be k
established and defined from the highest management levels through intermediate levels to and including 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 - GPUN shall have corporate responsibility for overall plant nuclear safety and shall take measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.
6.2.2 FACILITY STAFF l
6.2.2.1 The Vice President & Director Oyster Creek shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
6.2.2.2 The facility organization shall meet the followings a.
Each on duty shift shall include at least the following shift staffing:
One (1) group shift supervisor Two (2) control room operators Three (3) equipment operators - one may be a Radwaste Operator b.
At all times when there is fuel in the vessel, at least one licensed senior reactor operator shall be on site and one licensed reactor operator should be at the controle.
c.
At all times when there is fuel in the vessel, except when the reactor is in COLD SHUTDOWN or REFUEL modes, two licensed senior reactor operators and two licensed reactor operators shall be on site, with at least one licensed senior reactor operator in the control room and one licensed reactor operator at the controls.
i OYSTER CREEK 6-1 Amendment No.:
54,59,65,69,102
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At lea;t two licensed reatt:r oper; tors Ch311 be in the contr:1 room H.
g during all reactor startups, shutdowns, and other periods involving i
planned control rod manipulations.
I e.
All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel-Handling who has no other concurrent responcibilities during this operation.
f.
An individual qualified in radiation protection measures shall be on site when fuel is in the reactor.
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l g.
A Fire Brigade of at least 5 members shall be maintained onsite at all l
time. The Fire Brigade shall not include the minimum shift crew necessary for safe shutdown of the facility or any personnel required for other essential functions during a fire emergency.
i h.
Each on duty shift shall include a shift Technical Advisor except that the Shift Technical Advisors position need not be filled if the reactor is in the refuel or shutdown mode and the reactor is less than 212'F.
1.
Administrative procedures shall be developed and implerented to limit the working hours of unit staff who perform safety-related functions.
In the event that unferseen problems require substantial amounts of overtine to be used or during extended periods of shutdown for refueling, major maintenance or major pinnt modifications, on a temporary basis, the following guidelines shall be followed:
a.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
b.
An individual should not be permittod to work more than i
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l
in any 48-hour period, nor more than 72 hourt in any seven day period, all excluding shift turncier ti.na.
c.
A break of at least eight hours should be allowed between work periods, including shift turnover time.
d.
In a, b, ar,d c above, the time required to complete shift turnover is to be counted as break time and is not to be counted as work time.
e.
Except during extended shutdown peric;s, the use of overtina should be considered on an individual basis and not for the entire staff on a shift.
L Any deviation from the above guidelines shall be authorized by the Department Managers, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
OYSTER CREEK 6-2 Amendment No.:
92,102 l
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- j. The Manager P1Cnt oper;tions Cnd the Croop Shift Supervisor require
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Senior Reactor Operators licenses.
The Control Room operators require j
a Reactor operators license.
l 6.2.2.3 Individuals who train the operating staf f and those who carry out the j
hee.lth physics and quality assurance function shall h6ve sufficient organisational f reedom to be independent of _ operational pressures, however, they may report to the appropriate manager on site.
6.3 Facility Raff Oualificatiltag 1
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 positions
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unless otherwise noted in the Technical Specifications. Licensed j
operators shall meet the supplemental requirements specified in l
Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees. Technicians and maintenance personnel who do not meet ANSI /ANS 3.1 of 1976, Section 4.5, are permitted to perform work for which qualification has been demonstrated.
6.3.2 The management position respor.sible for radiological controle shall meet or exceed the qualifications of Regulatory Guide 1.8
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(Rev. 1-R, 9/75). rach other member of the radiation protection organization for which there is a comparable position described in ANSI N18.1-1971 shall neet or exceed the minimum qualifications specified therein, or in the case of radiation protection technicians, they shall have at least one year's continuCJs I
experience in applied radiation protection work in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power stations and shall have been certified by the management position responsible for radiological controls as qualified to perform assigned functions.
This certification must be based on an NRC approved, documented program l
consisting of classroom training with appropriate examinations and i
documented positive findings by responsible supervision that the individual-has demonstrated his ability to perform each sF*cified
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procedure and assigned fonction with an understr.ncing of its basis and purpose.
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 plant design, response and analysis of the plant for transients and accidents.
OYSTER CREEK 6-2a
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' 6.4 TRhINING 6.4.1-A retraining program for operators shall be maintained under the direction of the Manager responsible for plant training and shall l
meet the requirements and recommendation of 10 CFR Part 55.
Replacement training programs, the content of which shall meet the requirements of 10CFR Part 55, shall be conducted under the direction of the Manager responsible for plant training for licensed operators and Senior Resctor Operators.
6.4.2 A' training program for the Fire Brigade shall be maintained under the direction of the Manager responsible for plant training.
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.
Implementing approvals shall be performed at the cognizant manager level or above.
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 change thereto, shall ba reviewed for adequacy by an individual (s)/ group other than the preparer, but who may be from the same division as the individual who prepared the procedure or change.
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OYSTER CREEK 6-3 Amendment No.:
69,78, 125 o
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't 6.541.2 Proposed change 3 t9 the Appendic 'A' TechnisS1 Spesific; tion) ch311 be T
L reviewed by a knowledgeable individual (s)/ group other than the i
individual (s)/ group who prepared the change.
I 6.5.1.3 Proposed modifications, that affect nuclear safety, to facility j
structures,. systems and components shall be designed by an individual / organization knowledgeable in the areas affected by the proposed I
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 Specificatione including the preparation and forwarding of reports covering evaluation and recommendations 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 Events requiring 24-hour written notification to the Commission 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 & Director Oyster Creek shall be performed by a knowledgeable individual (s)/ group.
6.5.1.8 The Security Plan and implementing procedures shall be reviewed by a know2edgeable individual (e)/ group other than the individual (s)/ group which prepared thwn.
6.5.1.9 The Emergency Plan and implementing priocedures shall bu reviewed by a knowledgeablo individual (s)/ group other than the individual (s)/ group which prepared them.
s 6.5.1.10 Review of every unplanned onsite release of radioactivo natorial to the environs including the preparation and forwarding of reporte covering i
evaluation shall be performed by a knowledgeable individual (s)/ group.
Recommendations and disposition of the corrective action to prevent recurrence shall be sent to the Vice President & Director Oyster Creek.
6.5.1.11 Major changes to radwaste systems shall be reviewed by a knowledgeable individual (s)/ group other than the individual (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-disciplinery review is necessary.
If deemed necetaary, 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 to whether or not 6.5.1.1 through 6.5.1.5 constitute an unreviewed safety question.
OYSTER CREEK 6-4 Amendment No.:
59, 125 l
f F4 BEDORDS 6.5.1.13 Written records of activities performed under specifications 6.5.1.1 through 6.5.1.11 shall be maintained.
l QUALIFICATIONS 6.5.1.14 Responsible Technical Reviewers shall meet or exceed the qualifications of ANSI N18.1-1978 Section 4.6 or 4.4 for applicable disciplines or have 7 years of appropriate experience in the field of his specialty.
Credit towards experience will be given for advanced degrees on a one for one basis up to a maximum of two years. These Reviewers shall be designated in writing.
6.5.2 INDEPENDENT SAFETY REVIEW FUNCTION 6.5.2.1 The Vice President of each division within CPU 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 performance of the activities under review, but who may be from the same functionally cognizant organization as the i
individual / group performing the original work.
6.5.2.3 GPU Nuclear Corporation shall collectively have or have access to the
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experience and competence required to independently review subjects in the following areese a.
Nuclear power plant cperatione b.
Nuclear engineering c.
Chemistry and radiochemirtry d.
Metallurgy l
e.
Nondestructive testing f.
Instrumentation and control g.
Radiologica.1 bafety h.
Ecchanical engineering 1.
Electrical engineering
- j. Administrative controle and quality assurance practices k.
Emergency plans and related organization, procedures and equipment 1.
Other appropriate fields associated with the unique characteristics of oyster Creek 6.5.2.4 consultants may be utilized as determined by the cognizant Vice President to provide expert advice.
OYSTER CRFEK 6-5 Amendment No.:
69
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' RESPONSIBILITIES l
S-6.5.2.5' The following subjects shall be independently reviewed by the functionally assigned divisions:
a.
Written safety evaluations of changes in the facility as described in i
the Cafety Analysis Report, of changes in procedurea as described in the Safety Analysis Report, and of tests or experimente not described in the safety Analysis Report, which are completed without prior NRC approval under the provisions of 10CFR 50.59(a)(1). This review is to verify that such changes, tests or experiments did not involve a change in the Technical Specifications or an unreviewed safety question as defined in 10CR 5.59(a)(2).
Such reviews need not be I
performed prior to implementation.
b.
Proposed changes in procedures, proposed changes in the facility, or proposed tests or experiments, any of which involves a change in the
. Technical Specifications or an unreviewed safety question as defined in-10CFR 50.59(c). Matters of thin kind shall be reviewed prior to i-submittal to the NRC.
c.
Proposed changes to Technical Specifications or license amendments l
related to nuclear safety shall be reviewed prior to submittal to the NRC for approval.
d.
Violations, deviations, and reportable events which require reporting to the NRC in writing.
Such reviews are performed after the fact.
Review of events covered under this subsection shall include results l
of any investigations made and the recommendations resulting from such investigations to prevent or reduce the probability of recurrer.co of thw event.
e.
Written summaries of audit reports in the areas specified in section 6.5.3 and involving safety related functions.
l f.
Any other matters involving safe operatJon of the nuclear power plant which a reviewer deems appropriate for consideration, or which is referred to the independent reviewers.
QUALIFICATIONS 6.5.2.6 The independent reviewer (s) shall either have a Bacn91er's Degree in Engineering or the Physical Sciences and five (5) years of ptofessional level experience in the area being reviewed or have 9 years of appropriate experience in the field of his specialty. An individual performing reviews may possess competence in more than one specialty area.
Credit toward experience will be i
given for advanced degrees on a one-for-one basis up to a maximum of two years.
RECORDS l
l 6.5.2.7 Reports of reviews encompassed in Section 6.5.2.5 shall be prepared, maintained and trarsmitted to the cognizant division Vice President.
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l OYSTER CREEK 6-6 Amendment No.:
69 l
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6.5.3.1 Audits of facility activities shall be performed under the cognizance l
of the Vice President - responsible for Quality Assurance. These audits shall encompass:
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a.
The conformance of facility operations to provisione contained within the Technical specifications and applicable licensa conditions at i
j least once per 12 months.
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- b..The performance, training and qualifications of the facility staff at 1 east once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in i
facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.
3 d.
The Facility Emergency Plan and implementing procedures at least once j
per 12 months.
[
e.
The Facility Security Plan and inplementing procedures at least once per 12 months.
f.
The Fire Protection Security Plan and implementing procedures at least once per 24 months.
g.
The performance of activities required by the Operational Quality Assurance Plan to meet the criteria of Appendix
'B',
10CFR50, at least once per 24 months.
t h.
The radiological envisconmental monitorini y.'o7tum and th.a results l
t% roof e.t least ones per 17 month %
1.
'the OFFSITE DOSE CAQULATION MANUAL rnd implewenting procedures at.
least once per 24 months.
- j. The PROCESS CONTROL PROGRAM and implei.enting procedures for radio-active wa7tes at least once per 24 months.
k.
Any other area of facility operation considered appropriate by the IOSRG or the Otfice of the President-GPUNC.
6.5.3.2 Audits of the following shall be, performed under the cognizance of the l
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 off-site 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.
OYSTER CREEK 6-7 Amendment No.:
69, 89, 108,117 l
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REOORDA 6.5.3.3 Audit reports encompassed by sections 6.5.3.1 ana 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 (TOSRG)
STRUCTURE 6.5.4.1 The IOSRG shall be e full-time group of engineers experienced in nuclear power plant engineering, operations and/or technology, independent of the facility staff, and located onsite.
QBGhNIZATION i
6.5.4.2 a.
The IOSRG shall consist of a Manager responsible for Nuclear Safety l
Assessment and staff members who meet the qualifications of 6.5.4.5.
Group expertise shall be multidisciplined.
b.
The IOSRG shall report to the Director responsible for Nuclear Safety l
l Assessment.
FUNCTION 6.5.4.3 The periodic review functions of the IOSRG shall include the following l
on a selective and overview basis
- 1) Evaluation for technical adequacy and clarity of procedures important to the safe operation of the f acility.
- 2) Evaluation of facility operatter.s from a safety perspectiva.
- 3) Assenoraent of f acility nuclear safety programs.
1
- 4) Assessment of the faellity performance regarding conformance to requiremente related to safety.
.5)
Any other matter involving safe operation of the nuclear power plant that the manager deems appropriate for consideration.
AUTHORITY 6.5.4.4 The IOSRG shall have access to the facility and facility records as necessary to perform its evaluations and assessments. Based on its reviews, the IOSRG shall provide recommendations to the management positions responsible for the areas reviewed.
l OYSTER CREEK 6-8 Amendment No.:
69, 108
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' QUALIFICATIONS
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6.5.4.5 IoshG engineers shall have eithsr (1) a Bachelor's Degree in l
Enginevring or appropriate Physical sulence and three years of professional level experience in the nuclear power field which may include technical supporting functions or (2) eight years of appropriate experience in nuclear i
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.
t RECORDS j
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 Vice i
President responsible for nuclear safety assessment, Vice President & Director l
Oyster Creek, and the management positions responsible for the areas reviewed.
6.6 EEPORTABLE EVENT ACTION f
6.6.1 The following actions shall be taken for REPORTABLE EVENT 8:
i a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50; and b.
Each REPORTABLE EVENT shall be reported to th ?ognizant manager and the cognizant division Vice President and "We Vice President &
Director oyster Creek. The functionally s'wnizan" aivision staff shall prepare a Licenssa Event Report (LER) s a wordance with the guidance outlined in 10 CFR 50.73(b).
Copies of all such reports 4
shall be cubmitted to the functionally cognizant division Vice l
l President and the Vice President & Director, oyster Creek.
6.7
$AFFTY Un[T_.VIQIlpj 6.7.1 The following actions nhall be taken in the event a safety Limit is violated:
a.
If any Safety Limit is exceeded, the renctor shall be shut down i
immediately until tha commission authorizes the resumption of operation.
b.
The Safety Limit violation shall bs reported to the Commission and the Vice President and Director Oyster Creek.
c.
A Safety Limit Violation Report shall be prepared. The report shall
.be submitted to the Vice President and Director Oyster Creek. This report shall describe (1) applicable circumstances preceding the violation,-(2) effects of the violation upon facility components systems or structures, (3) corrective action taken to prevent recurrence.
j.
i d.
The Safety Limit Violation Report shall be submitted to the Commission within 10 days of the violation.
OYSTER CREEK 6-9 Amendment No.:
69, 78, 84,117 l
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e g;
- 6s S PROCEDURES 6.8.1-Written procedures shall be established, implemented, and maintained j
that meet or exceed the requirements of tha Nuclear Regulatory Commission's I
Regulatory Guide 1.33 (the applicable revision is identified in the GPU Nuclear operational Quality Assurance Plan) and as provided in 6.8.2 and 6.8.3 below.
1 Written procedures shall be adopted and maintained to implement thes Process control Plan Offsite Dose Calculation Manual I
6.8.2-Each procedure and administrative policy of 6.8.1 above, and substantive changes thereto, shall be reviewed as described in 6.5.1.1 and approved as described in 6.5.1 prior to implementation and periodically as specified in the Administrative Procedures.
6.8.3 Temporary changes to procedures 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 of CPUNC Management Staff authotized under section 6.5.1.12 and knowledgeable in the area affected by the procedure.
For changes which may affect the operational status of facility systems or equipment, at least one of l
these individuals shall be a member of facility management or supervision holding a senior Reactor Operator's License on the facility.
c.
The change is documented, subsequently reviewed and approved an described in 6.c.2 within 14 days of implementation.
6.0 EEEQBU N9_BE2U2RFMENTS i
In cddition to the applicable reporting requirements of 10 CFR, the following e
identified reports shall be submitted to the Administrator of the NRC Region I office unlous otherwise noted.
6.9.1 ROUTINE REPORTE
?
A.
Startuo Report. A summary report of plant startup and power escalation testing shall ba submittoe 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 i
design or hhs been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
The report shall address each of the testo identified in the FSAR and shall in general 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 specified details required in license conditions based on other commitments shall be included in this report.
l OYSTER CREEK 6-10 Amendment No.:
69, 78, 84, 108, 125
q..
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Startup reporto shall be cubmitted eithia (1) 90 d:y3 f 211owing completion of the startup test program, (2) 90 days following
. 9 resumption or commencement of commercial power operation, or (3) months following initial criticality,.whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program,.and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
3 b.
Annual Exoosure Data ReDort.
Routine exposure data reports covering the operation of the f acility during the previous calendar year shall j
be submitted prior to March 1 of each year. Reports shall contain a tabulation on an annual basis of the number of station, utility, and
[
other personnel (including contractors) receiving exposures greater than 100 mrom/ year and their associated man rem exposure according to work and jca functions.
(This tabulation supplements the requirements of 10 CFR 20.407),
e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance l
(describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures tota 11Anq l
1ess than 20% of the individual total dose need not be accounted fo; In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work i
functions.
c.
Monthly Doeratino Rooort.
Routine reports of operating statistica and shutdown experience shall be submitted on a monthly basis which will l
include a narrative of operating experience, to the U.S. Noclear Regulatory Commission, with a copy to the Regional Office, no later than the 15th of each month following the calouder month coveted by the report.
d.. semiannggi,Agpiqqp,tj,ys Ef f1waAt Ja],,f gp Qgmnt, A report of radioactive materials released from thu statien during the procseding six mor.ths shall be submitted to the NRC wittin 60 days after Canuary I and July 1 of each year.
Each report shall include the following informa: ions l
. (1) a svnaary by calendar quarte
- Sad by radionuclide of the goantities of radioactive liquid and gaseous effluents from the
- Station, (2) a summary of radioactive solid waste shipped from the Station including:
(a) Physical description of the waste (b) classification of the waste, per 10 CFR Part 61 (c) solidification agent (if solidified)
(d) total volume shipped (e) total quantity of radioactive material shipped (curies)
(f) best knowledge of identify of principal radionuclides (3) a description of any changes to the PCP or ODCH, l
OYSTER CREEK 6-11 Amendment No.:
69, 108
F l
n.
c.s i,*. '*- *
(4) o cummary cf meterologirci dato collected Curing the year ch:11 be included in the report submitted within 60 days after January 1 of I
[,
each year. Alternatively, summary meterological data ray be i
retained by GPU Nuclear and made available to the NRC upon request.
l e.=
Annual Radiolooleal Environmental Renort A report of radiological
[
environmental surveillance activities during each year shall be submitted before May 1 of the following year.
Each report shall include the following information required in specification 4.16 for radiological environmental surveillance:
(1) a summary description of the radiological environmental monitoring
- program, (2) a map and a table of distances and directions (compass azimuth) of locations of sampling stations from the reactor, (3) results of analyses of samples and of radiation measurements, (In the event some results are not available, the reasons shall be explained in the report.
In the event the missing results are obtained, they shall be reported to the NRC as soon as is reasonable.)
l (4) deviation (s) from the environmental sampling schedule in Table 1
4.16.1.
(5) identification of environmental samples analyzed when instrumentation was not capable of meeting detection capability in Table 4.16.2.
1 (6) a sun:mery of the resulte of the land use survey, (7) 2 sunnary of the results of licensee participation in an NRC
[
approved inter-laboratory crosscheck program for environmental 1]
sarples.
(8) resulte of dose evoluntions to demonstrate compliance with 40 CFR t
Part 190.10a.
l 4
Easis:
6.9.1.e i
e An annual report of radiological environmental surveillance activities includes factual data summarizing results of activities required by the surveillance program.
In order to aid interpretation of the data, GPUN may choose to submit analysis of trends and comparative non regional radiological environmental data.
In addition, the licensee may choose to discuss previous radiological environmental data as well as the observed radiological environmental impacts of station operation (if any) on the environment.
6.9.2 REPORTABLE EVENTS The submittal of Licensee Event Reports shall be accomplished in accordance with the requirements set forth in 10 CFR 50.73.
OYSTER CREEK 6-12 Amendment No.:
69, 84, 108
47 g'
,4.
Y*
- 'l C.9.3 UNIOUR REPORTING REQUIREMENTS
'I special reports shall'be submitted to the appropriate NRC office within the l
l
. time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification.
{
"~
l y
a.
Materials Radiation surveillance Specimen Reports (4.3A) b.
Integrated Primary containnent Leakage Tests (4.5) c.
Results of required leak tests perforred on sealed sources if the
(
tests reveal the presence of 0.005 microcuries or more of removable i
contamination.
i d.
Inoperable rire Protection Equipment _ (3.12) t i
e.
Core Spray sparger Inservice Inspection (Table 4.3.1-9)
Prior to startup of each cycle, a special report presenting the results of the inservice inspection of the core Spray Spargers during each refueling outage shall be submitted to the Commission for review.
f.
Liquid radwaste batch discharge exceeding specification 3.6.B.1.
g.
Main condenser offgas discharge without treatment per Specification 3.6.D.1.
,4 h.
Dose due to radioactive liquid effluent exceeding Specification 3.6.J.1.
- i. Air dose due to radioactive noble gas in gaseous effluent exceeding i
specification 3.6.L.1.
1
- j. Air dose duc to radiodine and particulates exceeding 5pecification i
3.6.H.l.
i k.
Annual total dose due to raoloactive effluents exceeding Specification
' j.
3.6.N.1.
1.
Records of results of analysen required by the Radiological Enviro.% mental Monitoring Progrr.m.
4 m.
Failures and challenges to Relief and Safety Valvto 1
Failures and challenges to Relief and Safety Valve which do not L
constitute an LER will be the subject of a special report submitted to the Commission within 60 days of the occurrence. A challenge is defined as any automatic actuation (other than during surveillance or testing) of Safety or Relief Valves.
L l
L l
OYSTER CREEK 6-13 Amendment No.:
69, 78, 108
- q. s t
T : '*' *
- t.10 KROORD RETENTION h
)
6.10.1L The following records shall be retained at least five years a.
Records and logs of facility operation covering time interval at each f
power level.
1 b.
Records and logs of principle maintenance activities, inspections, repair and replacenent of principal items of equipment related to j
nuclear safety.
c.
All Licensee Event Reports.
- d.. Records of surveillance activities, inspections and calibrations required by these technical specifications.
e.
Records of reactor tests and experiments.
f.
Records of changes made to operating procedures.
g..
Records of radioactive shipments h.
Records of sealed source leak tests and results.
- i. Records of annual physical inventory of all source material of record.
l.
5.10.2 The following records shall be retained for the duration of the Facility Operating Licenseet a.
Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
+
b.
Recorda of ned and irradiated fuel inventory, fuel tranciers and atae/61y ternup distoricW.
1 r.
Itecords of f acility radiation and contamination surveys.
i d.
Records of radiction exposure for all individuals entering radiation control areas.
r*. Mecotds of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility compenents designed for a limited number of transients or cycles.
g.
Records of braining and qualification for current members of the plant
)
staff.
h.
Records of inservice inspections performed pursuant to these technical specifications.
OYSTER CREEK 6-14 Amendment Nos:
69, 108, 117 I
-ns 4
q i-1 1.
Record) cf rcviews performed f:r change 3 made to pr:codurco cr 1
equipment or reviews cf tests and experiments pursuant to 10 CFR I
50.59.
- j. Records of reviews by the Independent Onsite Safety Review Group.
k.
Records for Environmental Qualification which are covered under the
{
. provisions for paragraph 6.14.
1.
Records of the service lives of all snubbers, including the date at which the service life commences, and associated installation and maintenance records.
m.
Records of results of analyses required by the Radiological Environmental Monitoring Program.
I 6.10.3 Quality Assurance Records shall be retained as specified by the Quality Assurance Plan.
I 6.11 RADIATION PROTECTION PROGRAM i
Procedures for personnel radiation protection shall be prepared consistent with
- the requirements of 10 CFR 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
.6.12 (Deleted) 6.13 HIGil RADIATION AREA 6.13.1 In lieu of the " control device" or " alarm signal" required by para-graph 20,203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrom/hr but less than 1000 mram/hr shall be barricaded and conspicuously posted as a high radiation area and entranen thereto shall be controlled by requiring toquance of a Radiation Work Permit (RWP).
NOTE: Health 7by41cs personnel rhall be exempt from the P;tt 1seuance requirement duri.39 the perfonzAnce of their assigned radi6tiore protectior.
duties, provided they are folicwing plant radiation protection precedures for entry into high radiation areas.
An individual or group of individuals per.eitteo to enter such creas shall be provided with one or more of the follovrings s
a.
A radiation monitoring device which continuously indicates the i
radiation dose rate in the area, b.
A radiation monitoring device which continuously integrates the radia-i tion dose rate in the area and alarms when a pre-set integrated dose l
is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.
c.
A health physics qualified ind;.idual (i.e. qualified in radiation protection procedures) with a radiation dose rate monitoring device j
who is responsible for providing positive exposure control over the l
OYSTER CREEK 6-15 Amendment No.:
69, 100, 108
p.
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t
- ' [4 cetivitiO3 withis the cr 3 cnd who will perftrm periodio refittien surveillance at the frequency in the RWP.
The surveillance frequency j
will be established by the Director responsible for Radiological l
- controls, i
6.13.2 Specification 6.13.1 shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrom/hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of operations j
and/or radiation protection supervision on duty.
6.14 ENVIRONMENTAL QUALIFICATION A.
By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 " Interim staff Position on Environmental Qualification of Safety-Related Electrical Equipment," December 1979. Copies of these documents are attached to Order for Modification of License DPR-16 dated October 24, 1980.
B.
By no later than December 1, 1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.
6.15 INTEGRITY OF SYSTEMS OUTSIDE CONTAINKENT The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluido during a serious transient or accident to as low as practical levels. This program shall include the following:
- 1) Provisions estaollehing preventive maintenance and porAcdic visual L
inspection requireAents, and L
- 2) System leak test requirements, to the extent permitted by oystem de-l-
sign and r adiological condi'clons, for each system at a frequency not to L
exceed retualing cycle intervals. Tha systems subject to tr.is testieg are (1) Cora spray- (2) Containment Spray, (3) Reactor Water Cleanup, (4)
Isolation condenser and (5) Shutdown Cooling.
6.16 IODINE MONITORING i
L The licensee shall implement a program which will ensure the capability to 1
accurately determine the airborna iodine concentration in vital areas
- under accident conditions.
This program shall include the following:
I a.
Training of personnel,
[
- Areas requiring personnel access for establishing hot chutdown condition.
l OYSTER CREEK 6-16 Amendment No.:
69, 108 l
w I '
, 4-b.
Procedure] f!r monitoring, Cnd j
c.
Provisions for maintenance of sampling and analysis equipment.
6.17 POST ACCIDENT SAMPLING l
Tne following program shall be established, implemented, and maintained.
l A program has been established which will ensure the capability to obtain and i
analyse reactor coolant, radioactive iodines and particulates in plant gaseous i
effluents, and containment atmosphere samples under accident conditions. The program shall include the followings a.
Training of personnel in sampling and analysis b.
Procedures for sampling and analysis c.
Provisions for verifying operability of the System.
6.18 PROCESS CONTROL PLAN t
- a.. GPU may change the Process Control Plan provided each change is submitted to the Commission by inclusion in the Semiannual Radioactive-Material Release Report for the period in which the char.ge is made effective and contains:
(1) Sufficiently detailed information to support the rationale for the
- change, (2) a determination that the product waste form will conform to the requirements of 10 CFR Part 61.56.
b.
Change (s) shall become effective after review and approval in i
accordance with Section 6.8.2.
[
6.19 QFFSITE DOSE CALCL'LATION MANUAL a.- GPU aay make changes to the offsite Dose Calculation Manuel (oDOM) provided each change is subm.tted to the ccmmissicn in the Semianaual Radivactive Material Reledee Report for the period in which the change is more effectit'a, The submittal shall contains (1) suf ficiently detailed Jr.fermation to support the rationale for the change.
t (2) a determination tha-the change will not substentially reduce the abilit y of dozo calculations or setpoint determinatior. to assess co.nplia ice with Specifications, and s
b.
Change (s) shall become effective after review and approval in accor-dance with Section 6.8.2.
OYSTER CREEK 6-17 Amendment.:
69, 98, 108
r
^
7
'/
<i l
I"'
0 20 MAJOR CHANGES TO RADICACTIVE WASTE TREATHENT SYSTEMS f
4 a.
Each modification to a radioactive waste treatment system which doeb not involve an unreviewed safety questions i
c (1) Shs11 be performed in accordance with tho' provisions of 10 CFR Part 50.59, except (2) The description of the modification and a written safety evaluation which includes the bases for the change shall be L
submitted as part of the annual FSAR update, and (3) Shall become effective upon review and approval by the Vice President and Director.
l Basis:
6.20 The radioactive waste treatment systems are those systems described in the-Final Safety Analysis Report (FSAR) and amendments thereto that are used to maintain control over radioactive materials in liquid and gaseous effluents and in solid waste packages for shipment offsite to a radioactive waste disposal facility and that are required to meet-the conditions in Specification 3.6.B, 3.6.D, and 3.1.4.
The NRC is notified of major changes to these radioactive waste treatment systems under the provisions of 10 CFR Part 50.59 and Part 50.71, the FSAR update.
l b
J 1
l OYSTER CREEK 6-18 Amendment No.:
108
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