ML20039G020
| ML20039G020 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/29/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20039G021 | List: |
| References | |
| NUDOCS 8201150117 | |
| Download: ML20039G020 (39) | |
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'o UNITED STATES 8% )
~1, NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 y'
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GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 0YSTER CREEK NUCLEAR GENERATING STATION AMENDED PROVISIONAL OPERATING LICENSE Amendment No. 59 License No. DPR-16*
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amenonent filed by Jersey Central Power & Light Co@any and GPU Nuclear Corporation (the licensees), dated October 2, 1981, as supplemented December 4 and 16,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
Construction of the Oyster Creek Nuclear Generating Station (the facility) has been completed in conformity with Provisional Construction Permit No. CPPR-15, dated December 15, 1964, the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; D.
There is reasonable assurance (i) that the activities authorized by this amended license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; E.
The issuance of this amended license will not be inimical to the comon defense and security or to the health and safety of the public; F.
GPU Nuclear Corporation is technically qualified and Jersey Central Power & Light Cogany is financially qualified to engage in the activi-ties authorized by this amended operating license in accordance with a
gg the rules and regulations of the Comission;**
co o 28 mg N
- Previously revised by Amendment Nos. 3, 19, 38, 47 and 53.
b
- This amendment does not affect the previous finding that the owner, Jersey Central Power & Light Company, is financially qualified to obtain the necessary 00::
funds for the operation and safe shutdown, if necessary, of the Oyster Creek Ea Nuclear Generating Station.
The new operator, GPU Nuclear Corporation, derives its financial qualifications from the owner's to obtain the necessary funds for the operation of the facility.
a m
o _
G.
Jersey Central Power & Light Company has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements. and Indemnity Agreements", of the Commission's regulations, H.
The receipt, possession and use of source, byproduct and special nuclear materials as authorized by this amended license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70; and I.
The issuance of this amended license is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Provisional Operating License No. DPR-16, as amended, is hereby amended in its entirety and issued to GPU Nuclear Corporation and Jersey Central Power & Light Company to read as follows:
A.
This amended license applies to the Oyster Creek Nuclear Generating Station (the facility), a single cycle, forced circulation, boiling light-water reactor, and electric generating equipment (the facility).
The facility is located on Jersey Central's Oyster Creek site in Lacey Township, Ocean County, New Jersey, approximately sixty miles south of Newark and forty-five miles east of Philadelphia, Pennsylvania, and is described in license application Amendment No. 3, " Facility Description and Safety Analysis Report", as supplemented and anended, and the Environmental Report (Amendment No. 68 to License Application).
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses GPU Nuclear Corporation:
(1)
Pursuant to Section 104b of the Act and 10 CFR Part 50, " Licensing of Production and Utilization Facilities", to possess, use and operate Oyster Creek Nuclear Generating Station, and Jersey Central Power & Light Company to possess the Oyster Creek Nuclear Generating Station at the designated location on the Oyster Creek site in Ocean County, New Jersey, in accordance with the procedures and limitations set forth in this amended license; l
(2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear naterial as reactor fuel, in accordance with the limitations for storage and aaounts required for reactor operation, as described in the Facility Description and Safety Analysis Report, as supplemented and amended as of December 7,1976; i
i (3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use at any time any byproduct, source, and special nuclear materials as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation nonitoring equipment calibration, and as fission detectors in amounts as required;
, (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source.or special materials without restriction to chemical or physical form, for sagle analysis or instrument calibration or associated with radioactive apparatus or cogonents; and (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess such byproduct and special nuclear materials as may be produced by the operation of the facility, but not to separate such materials retained within the fuel cladding.
C.
This amended license shall be deemed to contain and is subject to the conditions specified in the following Comission regulations:
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Comission now or hereafter in effect; and is subject to the additional conditions specified below:
(1) Maximum Power Level GPU Nuclear Corporation is authorized to operate the facility at steady state power levels up to a maximum of 1930 megawatts (thermal).
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
, are hereby incorporated in the amended license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
(3)
Reports GPU Nuclear Corporation shall make certain reports in accordance with the requirements of the Technical Specifications.
(4)
Records GPU Nuclear Corporation shall keep facility operating records in accordance with the requirements of the Technical Specifications.
(5)
Fire Protection GPU Nuclear Corporation may proceed with and is required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.23 of the NRC's Fire Protection Safety Evaluation (SE) on the facility dated March 3,1978, and supplements thereto. These modifications shall be cogleted as specified in Table 3.1 of the SE,, and supplements thereto.
, (6)
Physical Protection GPU Nuclear Corporation shall maintain in effect and fully implement all provisions of the following Comission-approved documents, including amendments and changes made pursuant to the authority of' 10 CFR 50.54(p), which are being withheld from public disclosure pursuant to 10 CFR 2.790(d):
(a) Security Plan collectively titled "0yster Creek Physical Security Plan", dated December 7,1977, as revised June 16, 1978, February 14,1979, June 26,1979, and August 21, 1979.
(b) Contingency Plan identified as "0yster Creek Safeguards Contingency Plan, Revision 1",
transmitted by letter dated June 3,1980, submitted pursuant to 10 CFR 73.40. The Contingency Plan shall be fully inplemented, in accordance with 10 CFR 73.40(b), within 30 days of this approval by the Comi ssion.
(c) Guard Training and Qualification Plan identified as "Dyster Creek Nuclear Power Plant Guard Training and Qualification Plan", submitted by letter dated July 28, 1980, as revised 1
January 7,1981.
This plan shall be fully inplemented in accordance with 10 CFR 73.55(b)(4) within 60 days of this approval by the Comission.
All security personnel shall be qualified within two years of this approval.
(7) GPU Nuclear Corporation shall replace all core spray spargers during the 1981 refueling outage as described in the NRC's Staff Safety Evaluation dated May 15, 1980.
3.
The effectiveness of this amended license is encompassed within the effective period which has been specified for the existing license:
This license is effective as of the date of issuance and shall expire at midnight April 9,1972.*
4.
This license amendment shall become effective January 1,1982.
FOR THE NUCLEAR REGULATORY COMMISSION Ndk AlaAn Dennis M. Crutchfield, Chief Operating Reactors Branch #5 v
Division of Licensing
- The license remains effective since a timely application dated March 6,1972, has been filed for a Fu'il Term License.
Attachment:
Changes.to the Technical Specifications Date of Issuance: December 29, 1981 9
l l
ATTACHMENT TO LICENSE AMENDMENT N0.59 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages of Appendices A and B Technical Specifications with the enclosed pages. The revised pages are identified by captioned amendment number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES*,
Appendix A Appendix A 11 11 6 6-31 6 6-26 Aypendix B Appendix B 5 5-5 5 5-5
- There were no. changes to the provisions contained on the following pages; they are merely included for pagination purposes:
6-17 through 6-22.
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Seqtien 4 Survaillance Requirembnts Page..
h
-A s
4.1 Protective Instrumentation 4.1-1
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4.2 Reactivity Control
~~ >~~~~~ t'.4_}1' 4.3 ' 7 2 4.2-1 4.3 Reactor Coolant 4.4 Emergency Cooling 4.5 Containment 4.5-1 4.6 Radioactive Effluents 4.6-1 4.7 Auxiliary Electricak Power 4.8-1 4;7-1 4.8 Isolation Condenser 4.9 Refueling 4.9-1
-4.10 ECCS Related Core Limits 4.10-1 4.11 Sealed Source Contamination 4.11-1 4.12 4.12 Fire Protection 4.13 Accident Monitoring Instrumentation 4.13-1 Section 5 Design Features 5.1 Site 5.1-1 5.2 Containment 5.2-1 5.3 Auxiliary Eouipment 5.3-1 Section 6 Administrative Controls 6.1 Responsibility 6-1 6.2 Organization' 6-1 6.3 Facility Staff Qualifications 6-2 6.4 Training 6-7
'('
6.5 Review and Audit 6-7[
6.6 Rebortable Occurrence Action 6-13. -
6.7 Safety Limit Vilation, 6-13 6.8 Proceddres 6-16 6.9 Reportir.g leauirements 6-16 6.10 Record Retentien 6-23 6.11 Radiation Pr.otection Prooram
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6-24 6.12 (Deleted) 6.13 Hich Radiation Area 6-24 6.14 Environmental Qualification 6 25
- 6.15 Integrity of Systems Outside Containment 6-25 6.16 Iodine Monitoring 6-26
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" Issued by N'RC Order d'te'd 10-24'-80.
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a 4
Amendment No. Jp, pf, f 59
.j
ADMINSTRATIVE CONTROLS 6.1 RESPONSIBILITY
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6.1.1 The Director Station Operations shall be responsible for overall l
f acility operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION 6.2.1 0FFSITE The organizalon for GPU Nuclear Corporation for management and technical support shall be functionally as shown on Figure 6.2.1.
6.2.2 FACILITY STAFF The facility organization shall be as shown on Figure 6.2.2 and:
Each on duty shift shal,I include at least the shift staffing a.
Indicated on Figure 6.2.2.
b.
At least one licensed reactor operator shall be in the control room when fuel is in the reactor.
c.
Two licensed reactor operators shall be in the control room dur i ng al l reactor startups, shutdowns, and other periods involvinc planned control rod manipulations.
I d.
ALL CORE ALTERATIONS shall be directly supervised by either a Iicensed Senior Reactor Operator or Senior Re' actor Operator' Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
e.
An Individual qualified in radiation protection measur'es shall be on site when fuel is in the reactor'.
f.
A Fire Brigade of at least 5 members shall be maintained onsite at all time. The Fire Brigade shall not include the minimum shi f t crew necessary for saf e shutdown of the unit or any personnel required for other essential functions during a fire emergency.
g.
Each on duty shift shall include a Shif t 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 4
less than 212*F.
Amendment No. 29, 40, E0, H, 59
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GPU NUCLEAA CORP.
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SUPPO47 OTSTER CAttu IpWCLtAA SAFtiY A99tSStethT cent CTom Amendment No.' J0, J7. M. 50, 59 '
6.la
NOTES TO FIGURE 6.2.1 1.
The President of the GPU Nuclear Corporation is a Senior Vice President of Met-Ed and is a Vice President of JCP&L. The Executive Vice President is a Vice President of both JCP&L and Med-Ed.
2.
The General Of fice Review Board reports to and gets general direction from the Of f ice of the President - GPU Nuclear Corporation. However,'the GORB has direct access to the Presidents, Chief Exocutive Of ficers and Boards of Directors of 'the Companies involved.
3.
The project engineering, the shift technical advisors, and licensing functions assigned to each nuclear plant site will report to the Vice President Technical Functions.
4.
The quality assurance, emergency planning and training functions assigned to each nuclear plant site will report to tha Vice President Nuclear Assurance.
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5.
The security, materials management, personnel and general administrative functions assigned to each nuclear plant site will report to the Vice President Administration.
6.
The radiological and of f site environmental control functions assigned to each nuclear plant site will report to the Vice President Radiological and Er.vironmental Controls.
6-16 AmendmentNo.NO,59 d
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s Amendment No. J0, 40, 50, 59 6-10 a
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c, 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 The members of the factiI.ty staff shalI meet or exceed the following qualifications:
Director Station Operations Requirements: Ten years total power plant experience of which t'hree ye'ars must be nuclear power plant experience.
A maximum of four years of academic training may f ut fiII four,of the remaining seven years of required experience. The Director must be capable of obtaining or possess a Senior Reactor Operator's License.
Plant Operations Director Requirements:
Eight years total power plant experience of which-three years must be nuclear power plant experience.
A maximum of two years of academic or related technical training may f ulfill two years of the remaining five years of required experiences The Plant Operations Director must be capable ~of obtaining or pos ass a Senior Reactor Operator's License.
Plant Engineering Director Requirements: Eight. years of responsible positions related to power generation, of which three years shall be nuclear power plant experience.
A maximum of four of the remaining five years of experience may be fulfilled by satisf actory completion of academic or related technical training.
Manager Plant Administration Requirements:
Eight years total power plant experience of which four years must have been i n nuclear power plant exper ience.
The Manager should possess a four year callege degree or equivalent in Business Administration or an Engineering discipline.
Manager Plant Operations
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Requirements:
Eight years total power plant experience of which three years must be nuclear power plant experience.- A maximum of two years of academic or related technical training ma.y fulti.Il two of the remaining five years of required experience.
The Manager Plant Operations must possess a Senior Reactor Operator's License.
Safety Review Manager
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Requirements:
Eight years total power plant experience of which three years must be nuclear power plant experience.
A maximum of two years of academic or related technical training may f ulfill two of the remaining five years of required experience.
6-2 Amendment No. Jp, N, pp, 50, 59 1
Manager Core Engineering At the time of initial core loading or appointment to the position, whichever is later, the responsible person shalI have a Bachelor's Degree in Engineering or the Physical Sciences and four years experience or a graduate degree and three years experience.
Two of these years shall be nuclear power plant experience. The experience shall be in such areas as reactor physics, core measurements, core heat transfer, and core physics testing programs. Successful completion of a reactor engineering training program (such as the 12 week concentrated programs v.'fered by NSS Vendors) may be equivalent to one year's nuclear power plant experience.,
Manager Plant Maintenance l
Requirements:
Seven years of total power plant experience of which one year must be nuclear power plant experience.
Two years of academ,1c or related technical training may fulfill two of the remaining six years of required experience.
Instrument Maintenance Supervisor Requirements:
Five years of experience'in instrumentation and control, of which a minimum of one year shall be in nuclear instrumentation and control at an operating nuclear power plant.
A maximum of four years of this five year experience may be f ul f il led by related technical or academic training.
Manager Plant Engineering The engineer in charge of technical support shall have a Bachelor's Degree in Engin,eering or the Physical Sciences and have three years of professional level experience in nuclear services, nuclear plant operation, or nuclear engineering, and the necessary overall nuclear background to determine when to call consultants and contractors for dealing with ccmplex problems beyond the scope of owner-organization expertise.
Mgr/ Deputy Radiological Controls (Reports Offsite)
Requirements: Bachelor's degree or the equivalent in a science or engineering subject, including some formal training in radiation protection.
Five years et professional experience in applied-radiation protection.
(Master's degree equivalent to one year experience and Do'etor's degree equivalent to two years experience where coursework related to radiation protection is involved.) Three ye.ars of this professional experience should be in applied radiation protection work in a nuclear f acility dealing with radiological problems similar to those encountered in nuclear power stations.
Chemistry Manager Requirements: Five years experience in chemistry of which a minimum of one year shalI be in radiochemistry at an operating nuclear power 6-6 Amendment i;o. 79, 60, E0, 59 c
[
m plant. A maximum of four years of this five year experience may be fulfilled by related technical or academic training.
Shift Technical Advisor Requirements:
Bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.3.2 Each member of the radiation protection organization for which there is a comparable position described in ANSI N18.1-1971 shatI meet or exceed the minimum qualifications specifled therein, or in the case of radiation protection technicians, they shal I have at least one year's continuous experience in applied radiation protection work in a nucleaar f acility dealing with radiological problems similar to those encodntered in nuclear power stations, and shall have been certifled by the Mgr/ Deputy Radiological Control s, as qual i f led to l perf orm assigned f unctions. This certification must be based on an NRC approved, documented program consisting of classroom training with appropriate examinations and documented positive findings by responsible supervision that the individual has demonstrated his ability to perform each specifled procedure and assigned function with an understanding of its basis and purpose.
6.4 TRAINING 6.4.1 A retr aining program for operators shal I be maintained under the direction of the Manager Plant Training Oyster Creek and shall meet l the requirements and recommendation of Appendix A of 10CFR 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 Plant Training Oyster Creek for licensed. l operators and Senior Reactor Oper.ators.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager Plant Training Oyster Creek.
l 6.5 SAFETY REYlEW AND AUDIT.
The Director Station Operations and three organizational units, the [
Plant Operations Review Committee (PORC), th~e Independent Safety Review Groups (ISRG) and the General Of fice Review Board (GORB) function to accomplish nuclear safety review and audit of the Oyster Creek Station.
- N' N' N' 6-7 O
6.5.1 DIRECTOR STATIC'N-@ERATIONS 6.5.1.1 FUNCTION
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The Director Station Operations shall ensure 'that:
l a.
All proposed changes to equipment or systems have been evaluated to determine if they constitute a change to the facility or procedures as described in the Safety Analysis Report.
b.
All proposed changes to equipment or systems that constitute a change of the f acility or procedures as described in the Safety Analysis Report have been evaluated to determine whether they involve an unreviewed safety question as defined in paragraph 50.59, Part 50, Title 10, Code of Federal Regulations.
c.
All proposed tests and experiments have been evaluated to determine whether or not they involve unreviewed safety questions as defined in paragraph 50.59, Part 50, Title 10, Code of Feder,al Regulations.
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6.5.1.2 AUTHORITY The Director Station Operations has the authority to:
l a.
Make a determination as to whether proposed changes to equipment, or systems involve a change to the procedures or f acility as described in the Safety Analysis Report.
b.
Make a determination as to whether or not proposed tests or experiments and changes to equipment or systems involve an unreviewed safety question.
c.
Direct the Plant Operations Review Committee to review safety evalutions of proposed changes to equipment or systems and safety evaluations of proposed tests and experiments to determine whether or not such changes, tests or experiments involve unreviewed safety questions.
NOTE:
Each determination that a proposed test, experiment, or change to a system or equipment that does not. involve an unreviewed saf ety question shall be reviewed by the independent Safety Review Groups to verify that the determination was correct.
This review shall be documented but is not a pre-requisite of the test, experiment, or change to a system or equipment.
6.5.1.3 RECORDS Any saf ety evaluations done in accordance with 6.5.1.1 (b) and (c) and any determinations made pursuant to 6.5.1.2(b) must be documented. Copies of these determinations shall be provided to the ISRG Coordinator and the Chairman of the General Of fice Review Board.
Records of all tests and experiments performed and all changes to equipment or systems made under the provislons of 10 CFR 6-8 Amendment No. 70, J7, 40,10, 59
Part 50.59 shall also be maintained at the station.
6.5.2 PLANT OPERATIONS REVIEW COMMITTEE (PORC) 6.5.2.1 FUNCTION The PORC shall function to advise the Director Station Operations.
l 6.5.2.2 COMPOSITION The PORC shall consist of the following plant, personnel:
Safety Review Manager Plant Operations Director Plant Engineering Director Manager Plant Maintenance Mgr/ Deputy Radiological Controls The Director Station Operations shall designate the Chairman and l Vice-Chairman from among the PORC members.
6.5.2.3 ALTERNATES Alternate members shall be appointed in writing by the PORC Chairman and will have the type of experience and training required of regular members.
However, they need not have the extensive longevity in the designated fields as long as in the opinion of the Chairman, their experience and judgement are adequate.
6.5.2.4 MEETING FREQUENCY The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or the Director Station' 0perations.
l 6.5.2.5 QUORUM A quorum of the PORC shall consist of the Chairman or Vice Chairman and three members / alternates. No more than two alternate members shall be counted in establishing a quorum.
6.5.2.6 RESPONSIBILITIES The responsibilities of the PORC are included in Table 6.5.1.
6.5.2.7 AUTHORITY a.
The PORC shall be advisory to the Director Station Operhtions.
Nothing herein shall relieve the Director Station Operations of hl.s responsibility or authority for overall safety operations including taking immediate emergency action. Determinations on items a and b of Table 6.5-1 shall be documented in writing.
b.
The PORC Chairman shall inmediately notify the Vice President l 6-9 Amendmen c No. J0, J7, 40, 50, 59,
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Page I of 2 TAst.E 6.5-1 e
Salt.TV ktNII.W RLSPONSiplLITIES IMDFPt40tv7 ut VIE W ITrM t1ti t Af. Arli m W
IN a) Proposed change to equipment.
Initiator: *bst prepare a conplete Fbst review items to nast review all Jeter.
May review any Jeter-or systems subject to the descript ion of stie prot =escJ clunges determine whether or not alnations by the minat ion, but mest Provisions of Section 50.59 and envere a sa fety ev.sluation of an unreviewed safety Director Station revles those for shit!
Part 50. Title 10 Code of the i-h nge is incliede l.
question is involved.'af Operations.
the* Director Statica FeJeral Regulations.
tilrector rtariac Oper:stions (1) requircJ by the Director th* erat ions has re.
nest Jetermine if the item is an Station Operations.
.tusstcJ Copa resiew.
as t ual (l.ang e to e.g elgeent or Systems as descrlhcJ in tt.c FSAR.
(2) Pnut Jettraine i f the item involves an unrecit=cJ safety ques
- lon. (3) nsy request the PORC to assist in the above determina-tions.
b) Proposed tests anJ experiments.
Initiatur: lbst prepare a eneplete
%st review item to to above.
As above.
(subject to provisions of) description of the proposed test Jetermine whether or not 50.59. Part $0. Title 10. Code or cas-riment and ca.us s e a sa fe t y an unreviewed safety of Federal Segulations, evaluat i..n of the t e st or emperi-peestion is involved, if ment is includcJ.
requested by the Director Dire ct or Stat ion (4.cr it ions (1)
- itation Operations.
Sbst sietermine if the lire involves an aanrev ie=cJ safet y q.or.t ion.
(2) Flay re.paest the l'tHT to assist in the above determen.itlons.
c) Prcrosed changes in Technical Initiator: nsit prepare ene.
II) tbst review the item Mast review change and Riy review say item Speelfications or in the NRC plete Joscription of the progesed for nnetear and raJIolo.
PORC recommenJation liut a. asst review those Operating License, ch.enge an.f ensure. a 5.st'et y evalu-r.ical safety. G) Must prior to outelttet to for thlch the l'irestor allon of the chans;'e is incliktnl.
3.ite recuanetitdatintis to the NetC, Elslips operations of e
ihr filtetter 9tatlett his supertinct have tevations as to shether requesteJ 4:0Hh review, iir not the change is safe.
J) Reportable occurrences tilrn tor stat ion oper.it inns 4 nist f est rcelew hernrishle nest review Rejertable As above.
W e enrest igat ions leerfom.J for ecurrences Relert for Occurrence Brports for all lirpnrtsble Dernrren.cs an.t a
.arcty significance anJ s.efety stealfisance and report preparcJ includent rl.e nLe reconnnerJ4tlims in revir Inc resonncemla.
.:sfety significance of the inclJent. t he leirectnr St.it ion v iims.
- p. rat ions on Imw to. an.e.1
'ivurrence.
6-14 Amendment No. //n &J4 59
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Page 2 of 2 TABt.F. 6.5 1 (ON'T)
SAFETY RI.Yll'W RisitNSIBILITIES
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tWFPtNDrNT R[VIIW ITDI INIT! AI AfTI(Pi Mnf fWl fMR3 e) Facility operations incluJing Continulag responsibility See Item i below As above Security Plan leergener Plan and laptementing procedures; review is to Jetect potential safety hatards.
f) Significance operation Director. Station Operations Report Review matter and report Perform indepenJest As above atmoraalleles or deviations from such mat ters to the PORC ISRG evaluation of safety review of PORC nornal and especteJ perf6rmance.
Coordinator and the Chairman G)RB.
significance to the ISRC evaluation.
and CORB.
g) Any indication of an unan.
As above As above
.to alove As above ticipated Jeficiency in scoe sapeet of Jssign or operation of safety related stratures, systems or component s.
)
Review to determin
- If As above h) IV)RC minutes anJ reporta.
any matters dissussed involve unrelated safety quest ions.
lieview to determine if The report of the j) Audit Reports and NRC Inspection Reports, any matters reported manageacut review of Involte Violations of the Q4 Plan, initt.
rechnica! Specification, sted by the Vice Ilcen*e re pi6 rement s or President, and Illrector s.
regislatloets or have any Oyster freen in accor.
wclear or #4Jiation-dance milh the Opera.
.arcty implicatlant.
tional Qaality As.
surance Plan, shall be rerlesed by the CORR hith respect to technical and admini.
strative safety issws.
Amendment No.'77, #, N, 59 6-15
and Director Oyster Creek and the Chairman of the GORB of any
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disagreements between the PORC and the Director Station Operations.
However, the Director Station Operations shall have the responsibility for resolution of such disgreements pursuant to 6.1.1.
6.5.2.8 RECORDS The PORC shall maintain written minutes of each meeting and copies' of minutes and determinations shall be provided to the Director Station Operations, Vice President and 0.irector Oyster Creek, ISRG Coordinator, and the Chairman of the GORB.
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6.5.3 INDEPENDENT SAFETY REVIEW GROUPS (lSRG) 6.5.3.1 FUNCTION AND COMPOSITION The ISRG shall f unction under the direction of an ISRG Coordinator, who shall be appointed by the Vice President and Director Oyster Creek to provide safety reviews.
The Coordinator shall have available the competence to review problems in the following area:
a.
Nuclear Power Plant Operations b.
Nuclear Engineering c.
Chemistry and Radiochemistry
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d.
Metallurgy e.
Instrumentation and Control f.
Radiological Safety g.
Mechanical and Electrical Engineering,
h.
Quality Assurance Practices The Coordinator shall estab l i sh, as needed, groups of two or more individuals with the expertise required f or each topic to be reviewed.
6.5.3.2 CONSULTANTS Consultants shall be utilized as necessary to supplement the expertise available in the GPU Nuclear Corporation.-
l 6.5.3.3 RESPONSIBILITIES The speci fic responsibility to ensure accomplishment o.f independent safety review of the Director Station Operations determinat.lons l Involving saf ety questions is assigned to the ISRG Coordinator and is accomplishd by utilizing, as necessary, the f u l~ l scope of expertise availab.le in the GPU Nuclear Corporation s ta f,f,
l-consultants, contractors and vendors as appropriate.
Tab le 6.5-1 defines the specific independent safety review responsibiiities.
6.5.3.4 AUTHORITY The ISRG advises the Vice President and Director. 0yster Creek. 'It l has the authority to conduct reviews and investigations, which will 6-10 Amendment No. M, J/, H, 50,59
be documented.
1 6.5.3.5 AUDITS Audits of facility activities shall be performed under the cognizance of the Vice President Nuclear Assurance.
These audits l
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shalI encompass:
a.
The conformance of f acility operation to all provisions contained within the Technical Spec.ifIcations and applicable Iicense conditions at least once per year.
b.
The performance training and qualific'ations of the entire l facility staff at least once per year.
c.
The results of all actions taken to correct deficiences occurring in facilly equipment, structures, systemas or method of operation that affect nuclear safety at least once per six months.
d.
The Facility Emergency Plan and implementing procedures at least once per two years.
e.
The F6cility Security Plan and implementing procedures at least once per two years.
f.
Any other area of f acility operation considered appropria'te by the GORB or the Vice President and Director Oyster Creek.
l 6.5.3.6 RECORDS Written documentation of all independent safety reviews and investigations will be forwarded to the Director Station Operations, Vice President and Director Oyster Creek and the Chairman of the General Office Review Board. In addition, any reportable occurrence or item involving an unreviewed safety question which is identified by the ISRG will be documented and reported immediately to the above-mentioned persons.
The audit findings which result from all audits conducted in accordance with Section 6.5.3.5 shall be documented and reported to the above mentioned persons within 30 days af ter completing the audit.
Reports documenting corrective action will receive the same distribution and they will also be forwarded to the ISRG Coordinator.
6.5.4 GENERAL OFFICE REVIEW BOARD (GORB) 6.5.4.1 FUNCTION The technical and administrative function. of the GORB is to provide independent review of major saf ety issu.es,. to foresee potentially significant nuclear and radiation safety problems, arnd to advise the Office of the President on these matters.
l 64 Amendment No. J7, @, 50, 59
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6.5.4.2 COW OSITION Members of tne General Of fice Review Board shall possess extensive experience in their individual specialities and collectively have the competence in the following areas:
a.
Nuclear Power Plant Operations b.
Nuclear Engineering c.
Chemistry and Radiochemistr'y d.
Metallurgy e.
Instrumentation and Control f.
Radiological Safety g.
Mechanical and Electrical Engineering The Chairman and Vice Chairman shall be appointed by the Of fice of the President. (Neither shall be an individual with line responsibility for operation of the plant).
The Chairman shall designate a minimum of six additional members.
No more than a minority of the Board shall have line responsibility for operation of Oyster Creek Nuclear Generating Station..
6.5.4.3 ALTERNATES Alternate members shall be appointed in writing by the GORB Chairman and will have the type of experience and training required of regular members, however, they need not have the extensive longevity in the designated fields as long as, in the opinion of the Chairman, their experience and judgement are adequate.
6.5.4.4 MEETING FREQUENCY The GORB shal-l meet at least semi-anuall and any time at the request of the Chairman or the Of fice of the President.
j 6.5.4.5 QUORUM A quorum shall consist of the Chai.rnan or Vice Chairman and three members / alternates.
No more than one alternate member shall be counted when establishing a quorum and no more than a minority of the quorum shall hold line responsibility for operations of the Oyster Creek Station.
6.5.4.6 RESPONSIBILITIES a.
The primary' responsibility of the GORB is to foresee potentially significant nuclear and radiation safety problems and to recommend to the Of fice of the President how they may be avoided or mitigated. l b.
Carry out 1he s p e c i~f i c independent safety review 7 responsibilities listed in Table 6.5-1.
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6-12 Amendment No. Jp, J7, M, S' 59
w 6.5.4.7 AUTHORITY The GORB shall be advisory to the Of fice of the President and shall l have the authority to conduct reviews, audits, and investigations requested by the Of fice of the President or as deemed necessary by l the GOR 8 in the fulfIIIment of its responsibiiities.
6.5.4.8 AUDITS The report of the management review,of the QA Pran, initiated by the Vice President and Director Oyster Creek in accordance with the l Operational Quality Assurance Plan, shall be reviewed by the GORB with respect to safety and administrative safety issues.
6.5.4.9 RECORDS Minutes of each GORB meeting shall be recorded and approved by the GORB Chairman. Copies of approved minutes will be f orwarded to the Of f ice of the President, Vice President and Director Oyster Creek, Director Station Operations, PORC Chairman, and others designated by the GORB Chairman.
GORB recommendations to the Of f ice of the President will be documented in a letter from the GORB Chairman to the Of f ice of the President.
Included with eacts letter will be any dissenting opinions of members of the Board.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken in the event of a Reportable Occurrence:
a.
The Commission shall be notified.and/or a report submitted pursuant to the requirements of Specif ication. 6.9.
b.
Each Reportable Occurrence Report submitted to the Commission shall be reviewed by the Plant Operations Review Committee and submitted to the ISRG Coordinator, Director Station Operations, and Vice President and Director Oyster Creek.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
If any Safety Limit is exceeded, the reactor shall be shut down immediately until the Commission authorizes. the resumption of operation.
b.
The Saf ety Limit violation shall be reported to the Commission and the Vice President and Director Oyster Creek.
l 6-13 Amendment No. J0, J/, fD, 50, 59
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c.
A Safety Limit Violation Report shall be prepared.
The report shall be rov,lewed by the Plant Operations Review Committee and submitted to the. Director Station Operations and Vice President and Director Oyster Creek. This report shall ' describe (1) applicable cli cumstances preceding the violation, (2) ef fects of the violation upon f acility components systems or structures, and (3) corrective action taken to prevent recurrence.
d.
,The-Safety Limit Violation Report shall be submitted to the Commission within 10 days of the violation.
It shall also be submitted to the ISRG Coordinator.
6.8 PROCEDURES
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6.8.1 Written procedures shall be established, implemented, and maintained that meet or exceed the requirements of Section 5.1 and 5.3 of American National Standard N18.7-1972 and Appendix "A" of the
. Nuclear Regulatory Commission's Regulatory Guide 1.33-1972 except as provided in 6.8.2 and 6.8.3 below.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the Plant Operations Review Committee and approved by the Director Station Operations p r ior to l Implementation and periodically as specified in the Administrative Procedures.
6.8.3 Temporary change's 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 the supervisory staf f, at least one of whom possesses a Senior Reactor Operator's License.
c.
The change is documented, subsequently reviewed by the Plant Operations Review Committee and approved by the Director Station Operations as specified in the Administrative Procedures.
6.9 REPORTING REQUIREMENTS r.
In addition to the applicable, reporting requirements of 10 CFR, the following identified reports shall be submitted to the Director of the appropriate Regional Of fice of Inspection and Inforcement unless otherwise noted.
6.9.1 ROUTINE REPORTS a.
Startup Report.
A summay report of plant startup and power escalation -testing shall be submitted folbwing (.1) receipt of an 6-16 Amendrnent No. 10, 25, 40, 50, 59
operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a dif ferent design or has been manuf actured by a dif f erent fuel supplier, and (4) modifications that may have significantly altered the, nuclear, thermal, or hydraulic perf ormance of the p l ant.
The report shalI address each of the tests identif.ied 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 obtan satisfactory operation shall also be decribed.
Any additional specified details required in license conditions based on other commitments shall be included in this report.
Startup reports shall be submitted within (1) 90 ' days following completion of the startup test program, (2) 90 days f ol lowing resumption or commencement of commercial power operation, or (3) 9 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 resusnption or commencement of commercial power operation), supplemetary reports shall be submitted at least every three months until all three events have been completed.
b.
Annual Exposure Data Report.
Routine exposure data reports covering the operation of the unit during the previous calendar year shall be submitted prior to March I 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 mrem / year and their associated man rem exposure according to work and job f unctions (This tab u l at ion supplements the requirements of 10 CFR 20.407),
e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintence (describe maintence), waste processing, and refueling.
The dose assignment to various duty f unctions may be estimates based oa pocket dosimeter, TLD, or film badge measurements.- Small exposures totalling less than 20% of the individual total dose need not be eccounted for.
In the aggregate, at least 80% of the total whole boJy' dose recieved from external
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sources shall be assigned to spec!ric major work functions.
c.
Monthly Operating Report.
Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis which will include e n.arrative of operating experience, to the D i rector, O f f I ce b+ '.~anagement an d Program Co'fitE61','-D.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to'the Regional Office of I&E, no later than the 15th of each month following the calendar month covered by the report.
l 6.9.2 REPORTABLE OCCURRENCES l
Reportable occurrences, including corrective actions and measures to prevent reoccurrences, shall be reported to the NRC.
Supplemental l
reports may be required to fully describe fina1 resolution of i
6-17 Amendment No. Ipi, gJ,59 4
occurrence.
In case of corrected or supplemental reports, a lIcense event report shall be completed and reference shall be made to the original report date.
a.
Prompt Notification With Written Followup. The types of events listed below shall be reported as expeditiously as possible, but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, maligram, or facsimile transmission to the Director of the appropriate Regional Of fice, or his designate no later than the first working day following the event, with a written followup report within two weeks. The written followup report shall include, as a minimum, a completed copy of a licensee event repor,t form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide a complete explanation of the circumstances surrounding the event.
(1)
Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protecive function by the time a monitored parameter-reaches the setpoint specified as the limiting system setting in the technical specifications or f ailure to complete the required protective function.
NOTE:
Instrument drif t discovered as a result of testing need not be reported under this item but may be reportable'under items 2.a(5), 2.a(6), or 2.b(1) below.
l (2)- Operation of the unit or affected systems when any parameter or operation sucject to a limiting condition is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications.
NOTE:
If specified action is taken when a system is fou.,
T *, b e operating between the most conservative and the least conservative aspects of a limiting condition for operation listed in the technical specifications, the limiting condition for operation is not considered to have been violated and need not be reported under this item, but it may be reportable under item 2.b(2) below.
(3)
Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
NOTE:
Leakage of valve packing or gaskets within the limits for identified leakage' set forth in technical specifications need not be reported under this item.
(4) ' Reactivity anormal les, invol'ving disagreement with the predicted value of reactivity balance under steady state conditions during power operation, greater than or equal to 1%
Ak/k; a calculated reactivity balance indicating a shutdown margin less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if sub-critical, 6-18 Aihendment No. Si9
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e an unplanned reactivity insertion of more than 0.5% Ak/k or occurrence of any unplanned criticality.
(5) Failure or malf unction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the SAR.
(6) Personnel error or procedural Inadequacy which prevents or could prevent, by itsel f, the f ul fillment of the f unctional requirements of systems required to cope with accidents analyzed in the SAR.
NOTE: For items 2.a(5) and 2.a(6) reduced redundancy that does not result in a loss of system function need not be reported under this section but may be reportable under items 2.b(2) and 2.b(3) below.
(7)
Conditions arising from natural or man-made events that, as a direct result of the event require plant shutdown, operation of saf ety systems, or other protective measures required by technical specifications.
(8) Errors discovered in the transient or accident analyses or in methods used for such analyses as described in the safety report or in the bases for the technical specifications that or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
(9) Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the saf ety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that' require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
NOTE:
This item is intended to provide for the reporting of potentially generic problems.
b.
Thirty Day Written Reports.
T5e reportable occurrences discussed below shall be the subject of written reports to the Director of the appropriate Regional Of f ice within thirty days of occurrence of the* event.
The written report shall include, as a minimum, a complete copy of a licensee event report form.
l.nformation provided on the licensee event form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
(1) Reactor protection system or. engineered saf ety f eature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional 6-19 Amendment No. 59
requirements of affected systems.
(2)
Conditions leading to operation in a degraded mode permitted by a limiting condition f or operation or. p l ant shutdown required by a limiting condition for operation.
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NOTE: Routine surveillance testing, instrunnent calibration, or preventive maintenance which require system configurations as described in items 2.b(1) and 2.b(2) need not be reported except where test results themselves reveal a degraded mode as described above.
(3)
Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reacto,r protection systems or engineered safety feature systems.
(4) Abnormal degradation of systems other than those specified in item 2.a(3) above designed to contain radioact.ive material resulting from the fission process.
NOTE: Sealed sources or calibration sources are not included under this item.
Leakage of valve packing or gaskets within.the limits for identified leakage set forth in technical specifications need not be reported under this item.
6.9.3 UNIQUE REPORTING REQUIREMENTS Special reports shall be submitted to the Director of Regulatory Operations Regional Of fice within the 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.
Materials Radiation Surveillance Specimen Reports (4.3A) a.
b.
Integrated Primary Containment Leakage Tests (4.5) c.
Semi-annual reports specif ying ef f luent release shall be submitted to the NRC.,These reports shall include the following:
(1) Radioactive Effluent Releases A statement of the quantitles of radioactive effluents released from the plant with data summarized on a monthly basis following the format of USAEC Guide 1.21.
(a).
Gaseous Effluents 1.
Gross Radioactivity Releases e.
Total gross radioacti v ity (in curies),
primarily noble and activatilon gases.
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6-20 Amendment 'No. 59
b.
Maximum gross r'adioactivity. release rate during any one-hour period.
c.
Total gross radioactivity (In curies) by nuclide release based on representative isotopic analyses performed.
d.
Percent of technical specification limit..
2.
lodine Releases -
a.
Total Iodine radioactivity (in curies) by nuclide released based on representative Isotopic analyses performed.
b.
Percent of technical specification limit for 1-131 released.
'3.
Particulate Releases a.
Total gross radioactivity (p,/3 released Cin curies) excluding background radioactivity.
b.
Gross alpha radioactivity released (in curies) excluding background radioectivity.
c.
Total gross radioactivity (In curies) of nuclides with half-lives greater than eight days.
d.
Percent of technical specification limit for particulate radioactivity with half-lives greater than eight days.
4.
Liquid Ef f luents a.
Total gross radioactivity (7/1 released (in curies) excluding tritium and average concentration released to the unrestricted area.
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b.
'The maximun concentration of gross radioactivity (7,jd released to the unrestricted area (averaged over the period of release).
' c.
Total tritium and total alpha radioactivity (in curies) released and average concentration released to the unrestricted area.
d.
Total dissolved gas radioactivity (in curies) and averaged concentration released to the unrestricted area.
e.
Total volume (in liters) of liquid waste released.
6-21 Amendment No. 59
f.
Total volume (in !iters) of dilution water used prior to release from the restricted area.
g.
Total gross radioactivity (in curies) by nuclide released based on representative isotopic analyses performed.
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h.
Percent of technical specification limit for total radioactivity.
(2).
Solid Waste (a). The total amount of solid waste shipped '(in cubic feet).
(b).
The total estimated radioactivity (in curies) involved.
(c). Disposition including date and destination.
(3).
Environmental Monitoring (a).
For each medium sampled during the reporting period, e.g.,
air, baybottom, surf ace water, soil, f ish, include:
1.
Number of samptIng locations.
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2.
Total number of samples.
3.
Number of locations at which levels are found to
.be significantly above local backgrounds, and 4.
Highest, lowest, and the average concentrations or level of radiation for the sampling point with the highest average and description of the location of that point with respect to the site.
(b).
If levels of radioactive materials in environment al media as determined by an environmental monitoring program Indicate the likelihood of public intakes in excess of 1%
of those that could result from continuous exposure to the concentration values listed in Appendix B, Table iI,Part 20 esti, mates of the likely resultant exposure,to individuals and to population groups, and assumptions upon which estimates are based shall be provided.
( c).-
If statistically significant variations of of f site evironmental concentrations with time are observed, correlation of these results with effluent release shall
)
be provided.
(d). Results of required leak tests performed on sealed sources if the tests reveal,the presence of 0.005 l
6-22 Amendment No. 59
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microcuries or more of removeab'le contamination.'
d..
Inoperable Fire Protection Equipment (3.12) 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.
6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of f acility operation covering time interval at each power level.
b.
Records and logs of principle maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
Reportable occurrence 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.
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h.
Records of sealed source leak tests and results.
1.
Records of annual physical inventory of all source material of record.-
6.10.2 The following records shall be retained f or the duration of the Facility Operating License:
4 a.
Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel Inventory, f uel transfers and -
assembly burnup histories.
c.
Records of f acility radiation and contamination surveys.
6-23 Amendment No. 59
d.
Records of radiation exposure for all Individuals entering radiation control areas.
Records of gaseous and liquid radioactive materia'l released to e.
the environs.
f.
Records of transient or operational cycles for those f acilitly components designed for a limited number of transients or cycles..
g.
Records of training and qualification for current members of the plant staff.
h.
Records of inservice inspections performed pursuant to these technical specifications.
1.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
.J.
Records of meetings of the Plant Operations Review Committee and the General Office Review Board.
t k.
Records for Environmental Qualification which are covered under the provisions of paragraph 6.14 6.10.3 Quality Assurance Records shall be retained as specified by the Quality Assurance Plan.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR 20 and shall ba approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 (Deleted) 6.13 HIGH RADIATION AREA 6 13.1 in Ileu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).
NOTE:
Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties,, provided they are following plant radiation protection procedures for entry into high radiation ares.
6-24 Amendment No. 59
An Individual or group of Individuals permitted to enter such areas shall be provided with one or more of the following:
A radiation monitoring device which continously indicates the a.
radiation dose rate in the area.
b.
A radiation monitoring device which continuously intergrates the radiation dose rate in the area and alarms when a pre-set integrated dose 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 knowledgeat.le of them.
c.
A health physics qualified Individual (i.e. qualified in radiation protection procedures) with a radiation dose' rate monitoring device who is responsible for providing positive exposure control over the activities within the area and who will perform periodic radiation surveillance at the frequency in the RWP. The surveillance frequency will be established'hy the Radiological Controls Manager.
6.13.2 Specification 6.13.1 shall also apply to each high radiation area in which the intensity of radiation is greater them 1000 anrem/hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shalI be nsaintained under the administrative control of operations and/or radiation protection supervision on duty.
6.14 ENVIRONMENTAL QUALIFICATION A.
By no later than June 30, 1982 all saf ety-related electrical equipment in the f aciiity shalI be qualifled. 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 Saf ety-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 aud itib l e 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 00R Guidelines or NUREG-0588.
Theraf ter, such records should be updated and imaintained current as equipment is replaced, further tested, or otherwise further qualified.
6.15 Integrity of Systems Outside Containment The licensee shall implement a program to reduce leakage from 6-25 Amendment No. 59
O systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:
1), Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2)
System leak test requirements, to the extent permitted by system design and radiological conditions, for each system at a f requency not to exceed ref ueling cycle intervals. The systems subject to this testing are (1) Core Spray, (2) Containment Spray, (3) Reactor Water Cleanup, (4) (solation Condenser and (5) Shutdown Cooling.
6.16 lodine Monitoring The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas
- under accident conditions. This program shall-include the following:
1.
Training of personnel, 2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
Areas requiring personnel access for establishing hot shutdown condition.
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6-26 Amendment No. 59
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o.
i APPENDIX B 1
TO FULL-TERM OPERATING LICENSE b
t ENVIRONMENTAL TECHNICAL SP'ECIFICATIONS FOR i
1 OYSTER CREEK NUCLEAR GENERATING STATION a!
d DOCKET NO. 50-219 I
i OCEAN COUNTY, NEW JERSEY JERSEY CENTRAL ' POWER & LIGHT COMPANY GPU NUCLEAR CORP 0 RATIO:1 N s November, 1978*
- Issued June 6, 1979 by Amendment No. 37-L Amendment No. 59
-l
5.0 ADMINISTRATIVE CONTROLS l
This section describes administrative and management controls established by the -
Applicant to provide continuing protection to the environment and to implement the environmental technical specifications.
5.1 Responsibility' I
Corporate responsibility for implementation of the Oyster Creek Environ-mental Technical Specifications and for assuring that plant op'erations. are controlled in such a manner as to provide continuing protection of the environment has been assigned by the Office of the President' to the Vice President and Director Oyster Creek.
Is The responsibility for conducting the studies as set forth in Section 3.1 I
(Non-Radiological Surveillance) and all of Section 4.0 (Special Surveillance Programs) rests with the GPUNC Manager, Environmental Controls.
Administrative measures are defined in Section 5.3 which provide that the individual or group responsible for auditing or otherwise verifying that an-activity has been correctly performed is independent of the individual or group responsible for performing the activity.
I 5-1 Amendment No. JA, 59 N
5.2 Organization The organization of the personnel responsible for implementation, audit, and review of the OCETS is shown in Figure 5-1.
~5. 3 Review and Audit Independent audit and review functions for environmental matters are the respensibility of the GPUNC Manager, Environmental Controls. This department reports directly to the Vice President and Director Radiological & Environmental Controls and is independent of line responsibility for the operation of the plant. The independent reviews and audits of the OCETS will be carried out by personnel from the Environmental Controls Department or by other personnel from GPUNC, GPUSC, I
outside contractors or consultants at the request of the Environmental Controls Department.
When individuals in the Environmental Controls Department of GPUNC perform l
any function relating to the OCETS other than independent audit and review, the Vice President and Director of Oyster Creek will ensure that an l
independent review and audit of that work is performed by another individual in the Environmental Controls Department or some other who is not directly l
responsible for the specific activity being reviewed and audited.
1
~
5-2 Amendment N'o.f50, 59 G
e
I q
I J
Office Of
~
The President General Offic Review Board l
I Vice President Vice President &
& Director Oyster Director Radiological Creek Controls ISRG i
~ ~ ~ -
Coordinator Mgr Environmental i
Controls 4
Director j
Station Operations l'
P1 ant Operations s
l Review Committee j
I 1
l Legend:
Direct Responsibility
Advisory Capacity i
d i
l FIGURE 5-1 ORGANIZATION FOR THE IMPLEMENTATIOK OF THE E.'tVIRONMENTAL TECHNICAL SPECIFICATIONS 5-3 Amendment No'. 50 59 1
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The. audits and reviews will be performed as required or requested bart in no case less than yearly.
The results of all reviews and audits will be documented in reports directly to the Vice President and Director Dyster Creek.
i Independent audits and ' reviews will encompass:
A.
Coordination of the OCETS with the safety technical specifications to avoid conflicts and maintain consistency.
B.
Compliance of station activities and operations with the OCET5..
C.
Adequacy of the programs and station procedures which are involved in ensuring the plant is operated in accordance with the OCETS.
D.
The proper functioning in accordance with the responsibilities listed in Section 5.1 of the OCETS.
1 E.
Proposed changes ~ to the OCETS and the evaluation of the impacts resulting from the changes.
I F.
Proposed written procedures, as described in Section 5.5.1 and 5.5.3 and proposed changes thereto which affect the environmental ingpact of the plant.
5-4 Amend 5ent No. 59 1
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f~
G.
Proposed changes or modifications to plant systems or equipment and a determination of the environmental impact resulting from the changes.
H.
Adequacy of the procedures described in Section 5.5.2 and the results obtained and conclusions drawn from the monitoring programs and special studies involved in the OCETS.
I.
Adequacy of investigations of violations of the OCETS and adequacy of and implementation of the reccmmendations to prevent recurrence of the violations.
5.4 Action To Be Taken If A Limiting Condition For Operation Is Exceeded i
km.
5.4.1 Any remedial action permitted by the OCETS will be taken until the limiting conditions can be met.
5.4.2 An investigation of the circumstances surrounding the violation of the limiting condition for operation will be initiated by the Director Station Operations and reviewed in accordance with Section 5.3.
5.4.3 A report of each occurrence of a violation of a limiting condition for operation of the OCETS will be prepared as specified in Section 5.6.2.
5-5 Amendment No. 56, 59
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