ML20154Q827

Proposed Tech Spec Pages 1.0-7,6-8,6-9 & 6-15,clarifying Existing Requirements & Providing Consistent Terminology

ML20154Q827
Person / Time
Site:	Oyster Creek
Issue date:	05/26/1988
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20154Q807	List: ML20154Q804 ML20154Q820 ML20154Q827
References
NUDOCS 8806070137
Download: ML20154Q827 (4)

Text

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1.39 REACTOR VESSEL PRESSURE TESTING System pressure testing required by ASME Code Section XI, ~ Article IWA-5000, including system leakage and hydrostatic tests, with reactor vessel completely water solid, core not critical and section 3.2. A satisfied.

1.40 SUBSTANTIVE CHANGES SUBSTANTIVE CHANGES are those which affect the activities associated with a document or the document's meaning or intent. Examples of non-substantive changes are: (1) correcting spelling, (2) adding (but not deleting) sign-off spaces, (3) blocking in notes, cautions, etc, (4) changes in corporate and-personnel titles which do not reassign responsibilities and which are not referenced in the Appendix A Technical Specifications, and (5) changes in nomenclature or editorial changes which clearly do not change function, meaning or intent.

0YSTER CREEK 1. 0-7 Amendment No.: 120 l

8806070137 880526 PDR ADOCK 05000219 P DCD 6269f

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. o 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 shall meet or exceed the minimum qualifications specified therein, or in the case of radiation protection technicians, they shall have at least one year's continuous experience in applied radiation protection work in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power stations and shall have been certified by the Radiological Controls Director, as qualified to perform assigned functions. 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 perfonn each specified procedure and assigned function with an understanding of its basis and purpose.

6.4 TRAINING 6.4.1 A retraining program for operators shall be maintained under the direction of the Manager Plant Training Oyster Creek and shall meet the requirements and recomendation of Appendix A of 10CFR Part 55. Repl acement 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 operators and Senior Reactor Operators.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager Plant Training Oyster Creek.

6. 5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL The Vice President of each division within GPU Nuclear Corporation as indicated in Figure 6.2.1, shall be responsible for ensuring the preparation, review, and approval of documents required by the activities described in 6.5.1.1 through 6.5.1.5 within his functional area of responsibility as assigned in the GPUN Review and Approval Matrix. Implementing approvals shall be performed at the cognizant manager level or above.

ACTIVITIES

6. 5.1.1 Each procedure required by Technical Specification 6.8 and other l procedures which affect nuclear safety, and substantive changes thereto, shall

be prepared by a designated individual (s)/ group knowledgeable in the area i affected by the procedure. Each such procedure, and substantive change thereto, shall be reviewed for adequacy by an individual (s)/ group other than the preparer, but who may be from the same division as the individaal who prepared the procedure or change.

0YSTER CREEK 6-8 Amendment No.: 69,78 6269f i

T 6.5.12 Proposed changes to the Appendix "A" Technical Specifications shall be reviewed by a knowledgeable individual (s)/ group other than the individual (s)/ group who prepared the change.

6. 5.1. 3 Proposed modifications, that affect nuclear safety, to facility structures, systems and components shall be designed by an individual / organization knowledgeable in the areas affected by the proposed modification. Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification but may be from the same division as the individual who designed the modification.~

6. 5.1. 4 Proposed tests and experiments that affect nuclear safety shall be reviewed by a knowledgeable individual (s)/ group other than the preparer but who may be from the same division as the individual who prepared the tests and experiments.

6. 5.1. 5 Investigation of all violations of the Technical Specifications including the preparation and fomarding of reports covering evaluation and recommendations to prevent recurrence, shall be reviewed by a knowledgeable individual (s)/ group other than the individual / group which perfomed the investigation.

6.5.1.6 Events requiring 24-hour written notification to the Commission shall be reviewed by an individual / group other than the individual / group which prepared the report.

6. 5.1. 7 Special reviews, investigations or analyses and reports thereon as requested by the Vice President & Director Oyster Creek shall be perfomed by a knowledgeable individual (s)/ group.

6. 5.1. 8 The Security Plan and implementing procedures shall be reviewed by a knowledgeable individual (s)/ group other than the individual (s)/ group which prepared them.

! 6. 5.1. 9 The Emergency Plan and implementing procedures shall be reviewed by a l knowledgeable individual (s)/ group other than the individual (s)/ group which

( prepared them.

6.5.1.10 Review of every unplanned onsite release of radioactive material to i the environs including the preparation and forwarding of reports covering evaluation shall be perfoned by a knowledgeable individual (s)/ group.

l Recommendations and dispo:,ition of the corrective action to prevent recurrence shall be sent to the Vice President & Director Oyster Creek.

6.6.1.11 Major changes to radwaste systems shall be reviewed by a knowledgeable individual (s)/ group other than the individual (s)/ group which l prepared them.

l 6.5.1.12 Individuals responsible for reviews performed in accordance with 6.5.1.1 through 6.5.1.4 shall include a determination of whether or not additional cross-disciplinary review is necessary. If deemed necessary, such review shall be perfomed by the appropriate personnel. Individuals responsible for reviews considered under 6.5.1.1 through 6.5.1.5 shall render i deteminations in writing with regard to whether or not 6.5.1.1 through 6.5.1.5 constitute an unreviewed safety question.

0YSTER CREEK 6-9 Amendment No. : 69 6269f

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6.8- PROCEDURES 6.8.1 .i Written procedures shall be established, implemented, and maintained that meet or exceed the requirements of the Nuclear Regulatory Comission's l Regulatory Guide 1.33 (the applicable revision is identified in the GPU Nuclear Operational . Quality Assurance Plan)'and as prov.ided in 6.8.2 and 6.8.3 below.

Written procedures shall be adopted and maintained to implement the:

Process Control Plan Offsite Dose Calculation Manual 6.8.2 Each procedure and administrative policy of 6.8.1 above, and substantive. changes thereto, shall be reviewed as described in 6.5.1.1 and approved as described in 6.5.1 prior to implementation and periodically as specified in the Administrative-Procedures.

6.8.3 Temporary changes to procedures 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered,

b. The change is approved by two members of GPUNC Management Staff authorized under Section 6.5.1.12 and kncwledgeable in the area L affected by the procedure. For changes which may affect the i

operational status of facility systems or equipment, at least one '

of these individuals shall be a member of facility management or supervision holding a Senior Reactor Operator's License on the facility.

c. The change is documented, subsequently reviewed and approved as described in 6.8.2 within 14 days of implementation.

6.9 . REPORTING REQUIREMENTS In addition to the applicable reporting requirements of 10CFR, the following identified reports shall be submitted to the Director of the appropriate l Regional Office of Inspection and Enforcement unless otherwise noted.

6.9.1 ROVIINE REPORTS l

a. Startup Report. A sumary report of plant startup and power l,

escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specified details required in license conditions based on other comitments shall be included in this report.

t OYSTER CREEK 6-15 6269f Amendment No.: 69, 78, 84, 108

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