ML20137E214

Amend 97 to License NPF-57,revising Section 6.0 of Plant TS to Relocate Requirements of Section 6.5 to QA Program & Other Listed Changes

ML20137E214
Person / Time
Site:	Hope Creek
Issue date:	03/21/1997
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Public Service Electric & Gas Co, Atlantic City Electric Co
Shared Package
ML20137E216	List: ML20137E214 ML20137E218
References
NPF-57-A-097 NUDOCS 9703270107
Download: ML20137E214 (18)

Text

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k UNITED STATES g

g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4001

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PUBLIC SERVICE ELECTRIC & GAS COMPANY i

ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. NPF-57 j

1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Public Service Electric &

l Gas Company (PSE&G) dated January 11, 1996, as supplemented by letters dated February 26, May 22, June 27, July 12, December 23, 4

-1996, and March 17, 1997, complies with the standards and i

requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance:

(i) that the activftie.5 authorized by this amendment can be conductwi without endanpHg tho health and safety of the public, and (ii) that ruch activitie wi'ti N conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; s

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Spect.fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is hereby amended to read as follows:

4 9703270107 970321 PDR ADOCK 05000354 P

PDR (2) Technical Soeqjfications and Environmental Protection Plan The TechnicaltSpecifications contained in Appendix A, as revised through Amendment No. 97, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.

PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

In addition, the license is amended to add paragraph 2.C.(14) to the Facility Operating license No. NPF-57 as follows:

(14) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 97, are hereby incorporated into this license.

Public Service Electric and Gas Company shall operate the facility in accordance with the Additional conditions.

3.

- This license amendment is effective as of its date of issuance and the change to the facility shall be implemented within 60 days from the date of issuance.

Implementation of this amendment shall include the relocation of certain technical specification requirements to the appropriate licensee-controlled documents as described in the Licensee's application dated January 11, 1996, and its supplements dated February 26, May 22, June 27, July 12, December 23, 1996, and March 17, 1997, and evaluated in the staff's safety evaluation attached to this amendment.

FOR THE NUCLEAR REGULATORY COMMISSION J

. Stolz, Direct Pr'o' ject Directorate 2

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:

1.

Pages 6 to License

• No. NPF-57 and page 1 to Appendix C of License

• No. NPF-57 2.

Changes to the Technical Specifications Date of Issuance: March 21, 1997

• Page 6 of the license and page 1 of Appendix C are attached, for convenience, for the composite license to reflect this change.

1 ATTACHMENT TO LICENSE AMENDMENT NO. 97 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 i

1.

Revise License as follows:

Remove Paae Insert Paae l

l 6

6 2.

Insert Appendix C, Page 1 a

3.

Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert xxiv xxiv xxy xxv xxVi 6-1 6-1 6-2 6-2 6-6 6-6 6-7 6-7 through 6-12 6-8 6-9 6-10 6-11 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-16 6-16 6-22 6-22 6-23 6-23 6-24 6-24

e-I (13) Safety Parameter Display System (Section 18.2. SSER No. 5)

Prior to the earlier of 90 days after restart from the first I

refueling outage or July 12, 1988, PSE&G shall add the following parameters to the SPDS and have them operational:

a.

Primary containment radiation b.

Primary containment isolation status c.

Combustible gas concentration in primary containment d.

Source range neutron flux (14) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 97, are hereby incorporated into this

license, Public Service E1cdric and Gas Company shall operate the facility in accordance with the Additional Conditions.

D.

The facility requires exemptions from certain requirements of 10 CFR l

Part 50 and 10 CFR Part 70. An exemption from the criticality alarm requirements of 10 CFR 70.24 was granted in Special Nuclear Material License No. 1953, dated August 21, 1985. This exemption is described in Section 9.1 of Supplement No. 5 to the SER.

This previously granted exemption is continued in this operating license. An exemption from certain requirements of Appendix A to 10 CFR Part 50, is described in l

Supplement No. 5 to the SER. This exemption is a schedular exemption to the requirements of General Design Criterion 64, permitting delaying i

functionality of the Turbine Building Circulating Water System-Radiation Monitoring System until 5 percent power for local indication, and until 120 days after fuel load for control room indication (Appendix R of SSER 5).

Exemptions from certain requirements of Appendix J to 10 CFR Part 50, are described in Supplement No. 5 to the SER. These include (a) an exemption from the requirement of Paragraph III.D.2(b)(ii) of Appendix J, exempting overall containment air lock leakage testing unless maintenance has been performed on the air lock that could affect i

air lock sealing capability (Section 6.2.6 of SSER 5); (b) an exemption

(

from the requirement of Paragraph III.C.2(b) of Appendix J, exempting main steam isolation valve leak-rate testing at 1.10 Pa (Section 6.2.6 of SSER 5); (c) an exemption from Paragraph III.D.3 of Appendix J, exempting Type C testing on traversing incore probe system shear valves (Section 6.2.6 of SSER 5); (d) an exemption from Paragraph III.D.2(a) of Appendix J, exempting Type C testing for instrument lines and lines containing excess flow check valves (Section 6.2.6 of SSER 5); and (e) an exemption from Paragraph III.C.2(a) of Appendix J,-exempting Type C testing of thermal relief valves (Section 6.2.6 of SSER 5). These exemptions are authorized by law, will not present an undue risk to the e

public health and safety, and are consistent with the common defense and I

security. These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto.

i These exemptions are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

t Amendment No. 44,97 I

APPENDIX C l

ADDITIONAL CONDITIONS OPERATING LICENSE NO. NPF-57 Public Service Electric and Gas Company and Atlantic City Electric Company shall comply with the following conditions on the schedules noted below:

Amendment Additional Condition Implementation l

Number Date 3

1 97 The licensee is authorized to relocate certain The amendment Technical Specification requirements to shall be licensee-controlled documents.

Implementation implemented of this amendment shall include the relocation within 60 days of these technical specification requirements from March 21, j

to the appropriate documents, as described in 1997 the licensee's application dated January 11, 1996, as supplemented by letters dated February 26, May 22, June 27, July 12, December 23, 1996, and March 17, 1997, and evaluated in the staff's safety evaluation attached to this amendment.

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Amendment No. 97 l

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INDEX ADMINISTRATIVE CONTROLS l

l SECTION PAGE 6.1 RESPONSIBILITY..........

6-1 l

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6.2 ORGANIZATION..............................

6-1 l

6.2.1 ONSITE AND OFFSITE ORGANIZATIONS...........

6-1 1

6.2.2 UNIT STAFF.............

6-1 i

Figure 6.2.1-1 (Deleted).........

6-3 Figure 6.2.2-1 (Deleted).

6-4 Table 6.2.2-1 Minimum Shift Crew Composition i

Single Unit Facility.............

L5 6.2.3 SHIFT TECHNICAL ADVISOR..............................

6-6 6.3 UNIT STAFF OUALIFICATIONS.................................

6-6 6.4 TRAINING........................

6-6 f.5 REVIEW AND AUDIT (THIS SECTION DELETED).........

6-6 i

6.6 REPORTABLE EVENT ACTION...

6-14 1

6.7 SAFETY LIMIT VIOLATION......

6-14 6.8 PROCEDURES AND PROGRAMS.................

6-15 6.9 REPORTING REOUIREMENTS...................................

6-17 6.9.1 ROUTINE REPORTS.

6-17 STARTUP REPORT........

6-17 JJRADU) REPORTS...................

6-17 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT..

6-18 RADIOACTIVE EFFLUENT RELEASE REPORT.................

6-19 MONTHLY OPERATING REPORTS...........................

6-20 i

CORE OPERATING LIMITS REPORT...................

6-20 i

l 6.9.2 SPECIAL REPORTS........

6-21 HOPE CREEK xxiv Amendment No.97

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l INDEX ADMINISTRATIVE CONTROLS i

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FECTION g

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l, 6.10 RECORD RETENTION........................................

6-21 j

J 6.11 RADIATION PROTECTION PROGRAM............................

6-22

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4 6.12 HIGH RADIATION AREA.....................................

6-23 1

1 6.13 PROCESS CONTROL PROGRAM (PCP)...........................

6-24

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6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)..................

6-24 l

6.15 MAJOR CHANGES TO RADIOACTIVE LIOUID. GASEOUS. AND SOLID WASTE TREATMENT SYSTEMS...........................

6-24 i

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I HOPE CREEK xxv Amendment No.97

6.0 ADMINISTRATIVE CONTROLS e=====au==========================u=====e==a=======e================u=========

6.1 RESPONSIBILITY 6.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Senior Nuclear Shift Supervisor, or during his absence from the control room, a designated individual shall be responsible for the control room command function. A management directive to this effect, signed by the seniorcorporatenuclearofficershallbereissuedtoallstationpersonnelonl an annual basis.

6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include positions for activities affecting the safety of the nuclear power

plant, i

a.

Lines of authority, responsibility, and communication shall be established and defined from the highest management levels through-intermediate levels to and including all operating organization positions.

These relationships shall be documented and updated, as appropriate in the form of organization charts, functional descrip-tions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Hope Creek Generating Station Updated Final Safety Analysis Report and updaced in accordance with 10 CFR 50.71(e).

b.

The plant manager 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.

c.

The senior corporate nuclear officer shall have corporate l

responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d.

The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

ElIT STAFF l

6.2.2 The unit organization shall be subject to the following:

l a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; 1

HOPE CREEK 6-1 Amendment No.97

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b.

At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Reactor I

operator shall be in the control room; c.

ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or licensed Senior Reaccor Operator Limited to Fuel Handling who has no other concurrent l

responsibilities during this operation; and l

d.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions e.g.,

licensed Senior Reactor Operators, licensed Reactor Operators, radiation protection technicians, equipment operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of over-time. The objective shall be to have operating personnel work a nominal ** 40-hour week while the unit is operating. Howe'rer, in the event that unforeseen problems require substantial amounts of over?ime to be used, or during extended periods of shutdown for refueling, ma]or maintenance on major unit mot' tications, on a temporary basis the following guidelines shall be followed:

1.

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.

2.

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 /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all excluding shift turnover time.

3.

A break of'at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time.

4.

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the appropriate department manager, or higher levels of management, in accordance with estab-t lished procedures and with documentation of the basis for granting the devia-tion. Controls shall be included in the procedures such that individual over-time shall be reviewed monthly by the plant manager or his designee to assure

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that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

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• • The shift schedule is based upon a 12-hour shift with a work week of either 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

. HOPE CREEK 6-2 Amendment No.97 i

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m ADMINISTRATIVE CONTROLS i

6.2.3 SHIFT TECHNICAL ADVISOR 5.2.3.1 The Shift Technical Advisor shall provide advisory technical support to the Senior Nuclear Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant anslysis with regard to safe operation of the unit. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific a

training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.

I 6.3 UNIT STAFF OUALIFICATIONS i

1 6.3.1 Each member of the unit staff shall meet or exceed the minimum

?

qualifications of ANSI /ANS 3.1-1981 for comparable positions, except for the individual designated as the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, the 4

individual designated as the operations manager who shall meet or exceed the minimum qualifications of ANSI /ANS 3.1-1981 except as modified by Specification 6.3.3, and the licensed operators who shall comply with the requirements of 10 CFR Part 55.

I 6.3.2 The Operations Manager or Assistant Operations Manager shall hold a g

senior reactor operator license. The Senior Nuclear Shift Supervisors, and l

Nuclear Shift Supervisors, shall hold a senior reactor operator license. The Nuclear Control Operators shall hold a reactor operator license.

6.3.3 The Operations Manager shall meet one of the following:

1 (1)

Hold a senior reactor operator license, or l

(2i lhve held a senior reactor operator license for this or a similar unit (BWR), or (3)

Have been certified at an appropriate simulator for equivalent senior operator knowledge.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall:

1) be maintained under the direction of the Director - Nuclear Training, 2) shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI /ANS 3.1-1981 for all affected positions except licensed operators, and 3) comply with the requirements of 10 CFR Part 55 for licensed operators.

1 6.4.2 A training program for the Fire Brigade shall be maintained under the-direction of the' Fire Protection. Manager and shall meet or exceed the-l requirements of the SRP (NUREG-0800) Section 13.2.2.II.6, 10 CFR 50 Appendix R and Branch Technical Position CMEB 9.5.1, Section C.3.d.

6.5 REVIEW AND AUDIT (THIS SECTION DELETED)

HOPE CREEK 6-6 Amendment No.97

ADMINISTRATIVE CONTROLS

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(PAGES 6-7 THROUGH 6-12 ARE DELETED) 1 1

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HOPE CREEK 6-7 through 6-12 Amendment No.97 f

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ADMINISTRATIVE CONTROLS

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Amendment No.97 HOPE CREEK 6-13

ADMINISTRATIVE CONTROLS e

I 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The commission shall be notified pursuant to the requirements of Section 50.72 to 10 CFR Part 50 and a report submittal pursuant to l

the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed by the Station Operations Review Comittee (SORC), and the results of this review shall be submitted to the Nuclear Review Board and the senior corporate nuclear officer.

6.7.

SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The senior corporate nuclear officer and the senior management position with responsibility for independent nuclear safety assessment activities and quality program oversight shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the SORC.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems, or structures, and (3) corrective action taken to prevent recurrence.

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c.

The Safety Limit violation Report shall be submitted to the Commission, the senior management position with responsibility for independent nuclear safety assessment activities and quality program oversight and the senior corporate nuclear officer within 30 days of the violation.

)

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

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HOPE CREEK 6-14 Amendment No.97

ADMINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

b.

The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto.

c.

Refueling operations.

d.

Surveillance and test activities of safety-related equipment.

e.

Security Plan implementation.

f.

Emergency Plan implementation.

g.

Fire Protection Program implementation.

h.

PROCESS CONTROL PROGRAM imp,ementation, i.

OFFSITE DOSE CALCULATION MANUAL implementation.

j.

Quality Assurance Program for effluent and environment monitoring.

6.8.2 Each procedure and administrative policy of 6.8.1 above, except 6.8.1.e and 6.8.1.f, and changes thereto, shall be reviewed and approved in accordance with requirements in Updated Final Safety Analysis Report (UFSAR) section 17.2 for SORC or for Technical Review and Control, as appropriate, prior to implementation and reviewed periodically as set forth in administrative procedures.

Procedures of 6.8.1.e and 6.8.1.f shall be reviewed and approved in accordance with the Facility's Security and Emergency Plans or requirements in Updated Final Safety Analysis Report (UFSAR) section 17.2 for Technical Review and Control, as appropriate, prior to implementation and reviewed periodically as set forth in administrative procedures.

6.8.3 On-the-Spot changes to procedures of Specification 6.8.1 may be made provided:

a.

The intent of the original procedure is not altered; b.

The change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator license on the unit affected; and c.

The change is documented and receives the same level of review and I

j approval as the original procedure within 14 days of implementation.

l HOPE CREEK 6-15 Amendment No.97

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ADMINISTRATIVE CO.NTROLS j

PROCEDURES AND PROGRAMS (Continued) j 6.8.4 The following programs shall be established, implemented, and 1

maintained:

a.

Primary Coolant Sources Outside Containment j

A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a r

serious transient or accident to as low as practical levels. The systems include the HPCI, CS, RHR, RCIC, Containment Hydrogen Recombiner, H2/02 analyzer, Post-Accident Sampling, Control Rod j

Drive Hydraulic (Scram Discharge portion) systems. The program shall l

include the following:

l 1.

Preventive maintenance and periodic visual inspection

.i requirements, and

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2.

A service pressure leak test for each system at refueling cycle intervals or less.

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b.

In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident

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conditions. This program shall include the following:

1.

Training of personnel, 1

2.

Procedures for monitoring, and 3.

Provisions for maintenance of sampling and analysis equipment.

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c.

Post-accident Samolina j

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A program which will ensure the capability to obtain and analyze reactor coolant, radioactive lodines and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions.

The program shall include the following:

1.

Training of personnel, 2.

Procedures for sampling and analysis, and 1

3.

Provisions'for maintenance of sampling and analysis equipment.

HOPE CREEK 6-16

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l ADMINISTRATIVE CONTROLS i

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RECORD RETENTION (Continued) h.

Records of annual physical inventory of all sealed source material of record.

6.10.3 The following records shall be retained for the duration of the unit Operating License:

i a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.

Records of radiation exposure for all individuals entering radiation c.

control areas.

d.

Records of gaseous and liquid radioactive material released to the

environs, e.

Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.

f.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members of the unit staff.

h.

Records of inservice inspections performed pursuant to these Technical Specifications.

i.

Records of quality assurance activities required by the Quality Assurance Program, j.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of SORC meetings and activities of the Nuclear Review Board (and activities of its predecessor, the Offsite Safety Review (OSR) staff).

1.

Records of the snubber service life monitoring pursuant to Technical Specification 4.7.5.

m.

Records of analyses required by the radiological environmental monitoring program which would permit evaluation of the accuracy of the analyses at a later date. This should include procedures effective at specified times and QA recorde showing that these procedures were followed.

6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.

HOPE CREEK 6-22 Amendment No. 97

ADMINISTRATZVE CONTROLS o

mammeOOmOmosamOmamOmmOOmamorummmmmmmmemoommmmmmmmmmmmmmmunosommmoomonanOOmOOOm 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10 CFR Part 20, each high radiation area in which the inten<

v of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr* shall i barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)**. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be j

made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.

c.

A radiation protection qualified individual (i.e.,

qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Supervisor in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose greater than 1000 mrem

• shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maincained under the administrative control of the Senior Nuclear Shift Supervisor on duty and/or the radiation protection supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate 4

levels in the immediate work area and the maxinum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in i hour a dose in excess of 1000 mrem

• that are located within large areas, such as the containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted, and a flashing light shall be activated as a j

warning device. In lieu of the stay time specification of the RWP, continuous surveillance direct or remote (such as use of closed circuit TV cameras), may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

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• Measurement.made at 18 inches from source of radioactivity.

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• • Radiation prot'ection personnel or personnel escorted by radiation protection I

personnel shall be exempt from the RWP issuance requireme.nt during the performance of their assigned radiation protection duties, provided they are i

otherwise following plant radiation protection procedures for entry into high radiation areas.

i HOPE CREEK 6-23 Amendment No.97 l

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ADMINISTRATIVE CONTROLS mammosammOOmemommmmmmmmmOmmmmmmmmmmmmmmmmmmmosammmmmmmmmmmmmmmmmmmmmmmmmmunomo

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6.13 PROCESS CONTROL PROGRAM (PCP) i

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6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee initiated changes to the PCP:

J 1.

Shall be submitted to the Commission in the Radioactive Effluent i

Release Report for the period in which the change (s) was made.

This submittal shall contain:

i a.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.

Documentation of the fact that the change has been reviewed and found acceptable by the SORC.

2.

Shall become effective upon review and acceptance by the SORC.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the ODCM:

1.

Shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:

a.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.

Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);

b.

A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determination; and c.

Documentation of the fact that the change has been reviewed and found acceptable by the SORC.

2.

Shall become effective upon review and acceptance by the SORC.

6.15 MAJOR CHANGES TO RADIOACTIVE LIOUID. GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.15.1 Licensee initiated major changes to the radioactive waste system (liquid, gaseous and solid):

1.

Shall be reported to the Commission in the UFSAR for the period in which the evaluation was reviewed by SORC.

The discussion of each change shall contain:

HOPE CREEK 6-24 Amendment No.97

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