ML20197G277

Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station

ML20197G277
Person / Time
Site:	Oyster Creek
Issue date:	12/23/1997
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20197G275	List: ML20197G269 ML20197G277
References
NUDOCS 9712300409
Download: ML20197G277 (7)

Text

. _ _ _

, ADMINISTRAT' J CONTROLS .

6.1 RESPONSIBILITY 6.l.1 The Vice President & Director Oyster Creek shall be responsible for overall fccility operation. Those responsibilities delegated to the Vice President &

Director as stated in the Oyster Creek- Technical Specifications may also be fulfilled by the Deputy Director. The Vice President & Director shall delegate in

' writing the succession to this responsibility during his and/or the Deputy Directors absence.

-6.2 QRGANIZATION 6.a.1 Corcorate 6.2.1.1 An onsite and offsite organization shall be established for unit operation cnd corporate management. The onsite and offsite organization shall include the pooitions for activities affecting the safety of the nuclear power plant.

6.2.1.2 Lines _ of authorit.y, responsibility and communication shall be established cnd defined from the highest management levels through intermediate levels to and including operating organization positions. These relatienships shall be documented cnd updated as appropriate, in the form of organizational charts. Thece organizational charts will be documented in the Updated FSAR and updated in cecordance with 10 CFR 50.71e. t 6.2.1.3 The President - GPU Nuclear shall have corporate responsibility for overall l

plant nuclear safety and shi:1 take measures needed to ensure acceptitble performance of the staff in operating, caintaining, and providing technical support in the plant co that continued nuclear safety is assured.

6.2.2 FACILITY STAFF 6.2.2.1 The Vice President & Director Oyster Creek shall be responsible for overall unit safe - operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

6.2.2.2 The facility organization shall meet the following:

a. Each on duty shift shall include at least the following shift staffing:

One (1) group shif t super;isor Two (2) control room operators Three (3) equipment operators - one may be a Radwaste Operator

b. At all times when there is fuel in the vessel, at least one licensed senior reactor operator shall be on site and one licensed reactor operator shoulo be at the controls,

c. At all times when there is fuel'in the vessel, except when the reactor is in COLD SHUTDOWN or REFUEL modes, two licensed senior reactor operators and two licensed reactor operators shall be on site, with at least one licensed senior reactor oper..to- in the control room and one licensed reactor operator at the controls, t

OYSTER CREEK 6-l' Amendment No.:54,59,65,69,102,134 1 9712300409 971223 7 PDR ADOCK 05000219 P PDR.

6.4 TI,< AINING -

6.4.1 A retaining program for operators shall be maintained under the direction of the Manager responsible for plant training and shall meet the requirements and recommendation of 10 CFR Part 55. Replacement training programs, the content of which shall meet the requirements of 10 CFR Part 55, shall be conducted under the direction of the Manager responsible for plant training for licensed operators and Senior Reactor Operators.

6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL The Vice President of each division within GPU Nuclear, Inc. shall be responsible for ensuring the l preparation, review, and approvsl of documents required by the activities described in 6.5.1.1 through 6.5.1.5 within his functional area of responsibility as assigned in the GPU Nuclear Review and Approval Matrix. Implementing approvals shall be performed at the cognizant manager level or above.

ACTIVITIES 6.5.1.1 Each procedure required by Technical Specification 6.8 and other procedures which affect nuclear safety, and substantive changes thereto, shall be prepared by a designated individual (s)/ group knowhdgeable in the area affected by the procedure. Each such procedure, and substantive change thereto, shall be reviewed for adequacy by an individualD)/ group other than the preparer. but who may be from the same division as the individual who prepared the procedure or change.

s OYSTER CREEK 6-3 Amendment No.: 69,78,125,134,161

\

.. . _ __m_________ _ . _- _ _ .

LRECORD,S l:;,- _

i 6.5.1.131 Written records of activities performed undhr spe:ifications 6.5.1.1 through 6.f.1.11 shall be

maintained.-

dUALI51 CATIONS -

6.5.1.14 Responsible Technical Reviewers shall meet or exceed the qualifications of ANSI /ANS 3.1-1978 Section 4.6 or 4.4 for applicable disciplines or have 7 years of appropriate experience in the Jfield of his specialty. Credit towards experience will be given for advanced degrees on a one-for-one ,

basis up to a maximum of two years. These Reviewers shall be designated in writing.

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6.5.2 INDEPENDENT SAFETY REVIEW

. FUNCTION 6.5.2.1 The Vice President of each division within GPU Nuclear, Inc. shall be responsible for ensuring -

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- the periodic independent safety review of the subjects described in 6.5.2.5 within his assigned area of -

safety review responsibility, ai assigned in the GPUN Review and Approval Matrix.

6.5.2.2 - Independent. safety review shall be completed 1 y an individual / group not having dbect responsibility for the performance of the activities under review, but who may be from the same functionally cognizant organization as the individual / group performing the original work.

6.5.2.3 GPU Nuclear, Inc. shall collectively have or have access to the experience and ccmpetence j required to independently review subjects in the following areas:

a. Nuclear power plant operations

b. Nuclear engineering

c. Chemistry and radiochemistry

d. Metallurgy

e. Nondestructive testing

f. Instrumentation and control

g. Radiological safety h.- Mechanical engineering

i. Electricalengineering

j. Administrative controls and quality assurance practices

k.' Emergency plans and related organization, procedures and equipment

1. Other appropriate fields associated with the unique characteristics of Oyster Creek

~ 6.5.2.4_ Consultants may be utilized as determined by the cognizant Vice President to provide expert

advice.

OYSTEK CREEK. 6-5 Amendment No.: 69,134,181

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! 6.5.3 AUDITS 6.5.3.1 Audits of facility activities shall be performed in accordance with the Oyster Creek Operational Quality Assurance Plan. These audits shall encompass:

a. ihe conformance of facility operations to provisions ccntained _within the Technical Specifications and applicable license conditions.

b. The perfonnance, training and qualifications of tl.e facility stalT.

c. The results of act;ons taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety.

- d. The Facility Emergency Plan and impleuenting procedures.

c. The Facility Security Plan and implementing procedures.

f. The Fire Protection Program and implementing procedures.

g. The performance of activities required by the Operational Quality Assurance Plan to meet the criteria of A ppendix 'B',10 CFR 50.

h. The rad:ological environmental monitoring program and the results thereof,

i. The OFFSITE DOSE CA'LCULATION MANUAL and implementing procedures.

j. The PROCESS CONTROL PROGRAM and implementing procedures for rcdioactive wastes.

k. Any other area of facility operation considered appropriate by the IOSRG or the Office of the President-GPU Nuclear. l 6.5.3,2 Audits of the following shall be performed under the cognizance of the Vice President -

responsible for technical support,

a. An independent fire protection and loss prevention program inspection and audit shall be performed utilizing either qualified licensee personnel cr an outside fire protection firm.

b. An inspection and audit of the fire protection and loss prevention program, by an outside qualified fire consultant.

' OYSTER CREEK 6-7 Amendment No.: 69,89,108,117,134,161,181 1

6.17 POST-ACCIDENT SAMPLING The following program shall be estabhshed, implemented, and maintained.

. A program has been established which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and contsinment atmosphere samples under accident conditions. The program shall include the following:

a. Training of personnel in sampling and analysis,

b. Procedures for sampling and analysis.

c. Provisions for verifying operability of the System.

6.18 ]$QCESS CONTROL PLAN

a. GPU Nuclear, Inc. initiated changes to the PCP:

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1. Shall be submitted to the NRC in the Annual Radioactive Effluent Release Report for the period in which the changes were made. This submittal shall contain:

a. sufficiently detailed information to justify the changes without benefit of additior.al or supplemental information;

b. a determination that the changes did not reduce the overall conformance of the

, solidified waste product to existing criteria for solid wastes; and

c. documentation that the changes have been reviewed and approved pursuant to Section 6.8.2.

2. Shrf become effective upon review and approval by GPU Nuclear Management.

4 6.19 OFFSITE DOSE CALCULATION MANUAL f) -

a. The ODCM shall be approved by the Commission prior to implementation.

b. GPU Nuclear, Inc. initiated changes to the ODCM shall be submitted to the NRC in *he l

Annual Radioactive Effluent Release Report for the period in which the changes were made. This submittal shall contain:

1. sufficienQ detailed information to justify the changes without benefit of additional or supplementalinformation;

~2. a determination that the changes did not reduce the accuracy or reliability of dose calculations or setpoint determination; and,

3. documentation that the changes have been reviewee and approved pursuant to Section 6.8.2.

c. Change (s) shall become effective upon review and approval by GPU Nuclear Management.

OYSTER CREEK 6-20 Amendment No.:69,98,108,134,166

'6 20 ' MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS

'" DELETED.

If.

_ OYSTER _ CREEK '6-21 Amendment No.: 108,166 l

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,n.i

.NUREG 04882 APPENDIX B -

TO PROVISIONAL OPERATING LICENSE NO'. DPR-16 ENVIRONMENTALTECHNICAI 3PECIFICATIONS FOR OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 OCEAN COUNTY, NEW JERSEY JERSEY CENTRAL POWER & LIGHT COMPANY d/b/a GPU ENERGY GPU NUCLEAR, INC.

NOVEMBER 1978*

n Olssued to the ASLB ca this date; issued by License Amendment No. 37, June 6,1979.

4 Amendment No.: 59, 66,'107