ML18010A717

Proposed Tech Specs Implementing Functional Role & Responsibilities of Recently Created Nuclear Assessment Dept

ML18010A717
Person / Time
Site:	Harris
Issue date:	08/06/1992
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18010A716	List: ML18010A715 ML18010A717
References
NUDOCS 9208140209
Download: ML18010A717 (20)

Text

ENCLOSURE 4 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO.

50-400/OPERATING LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT NUCLEAR ASSESSMENT DEPARTMENT FUNCTIONAL CHANGES PROPOSED TECHNICAL SPECIFICATION PAGES 208i402 g 05000400>>

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ADMINISTRATIVE CONTROLS

~ 3 PROJECT ASSESSMENT'(PA)

SECTION FUNCT

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u;@ ~.5.e) 6.2.3.1 Th PA Section shall function to examine unit operating characteristi NRC issuances, industry advisories (including information forwarded by INP from their evaluation of all industry LERs),

and other sources of unit des' and operating experience information, including units of similar design, wh h may indicate areas for improving unit safety.

The PA Section shall eke detax d recoranendations for revised procedures, equipment modifications, maintena'nce ctivities, operations activities, or other means of improving unit safety, to propriate levels of management, up to and including the Executive Vice Pre ident - Power Supply, if necessary.

COMPOSITION 6.2.3.2 The PA Section shall include at 1

st five, dedicated, full-time engineers located on site.

Each shall have baccalaureate degree in engineering or related science and at least 2 y rs professional level experience in his field, at least 1 year of which perience shall be in the nuclear field.

RESPONSIBILITIES 6.2.3.3 The PA Section shall be responsible for maintaining s

veillance of unit activities to provide independent verification that these a

ivities are performed correctly and that human errors are reduced as much as pra ical.

RECORDS 6 ' '.4 Records of activities performed by the PA Section shall be prepared, maintained, and forwarded each calendar month to the Manager " Nuclear Assessment Department.

6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Foreman in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

The Shift Technical Advi:sor shall have a baccalaureate degree or equivalent in a scien-tific or engineering discipline and shall have received specific 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.

6.3 Deleted

• Not responsible for sign-off function.

SHEARON HARRIS UNIT 1

6-6 Amendment No.

26

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ADMINISTRATIVE CONTROLS ualified Safet Reviewers (Continued)

These individuals shall have a baccalaureate degree in an engineering or related field or equivalent, and 2 years of related experience.

Such designation shall include the disciplines or procedure categories for which each individual is qualified.

Qualified individuals or groups not on the plant staff may be relied upon to perform safety reviews if so designated by the Plant General Manager.

6.5.1.4 Safet Evaluations and A

rovals 6.5.1.4.1 The safety evaluation prepared in accordance with Specification 6.5.1.1.1 shall include a written determination, with basis, of whether or not the procedures or changes

thereto, proposed tests and experiments and changes

thereto, and modifications constitute an unreviewed safety question as defined in Paragraph 50.59 of 10 CFR Part 50, or whether they involve a change to the Final Safety Analysis Report, the Technical Specifications, or the Operating License.

6.5.1.4.2 The safety evaluation shall be prepared by a qualified individual.

The safety evaluation shall be reviewed by a second qualified individual.

6.5.1.4.3 A safety evaluation and subsequent review that conclude that the subject action may involve an unreviewed safety question, a change to the Technical Specifications, or a change to the Operating License, will be referred to the Plant Nuclear Safety Committee (PNSC) for their review in accordance with Specification 6.5.2.6.

If the PNSC recommendation is that an item is an unreviewed safety question, a change to the Technical Specifications, or a change to the Operating License, the action will be referred to the Commission for approval prior to implementation.

Implementation may not proceed until after review by the Nuclear Assessment Department in accordance with Specification 6.5.3.9.

6.5.1.4.4 If a safety evaluation and subsequent review conclude that the subject action does not involve an unreviewed safety question, a change to the Technical Specification, or a change to the Operating License, the action may be approved by the Plant General Manager or his designee or, as applicable, by the Manager of the primary functional area affected by the action.

The individual approvi'ng the action shall assure that the reviewers collectively possess the background and qualification in all of the disciplines necessary and important to the specific review for both safety and technical aspects.

To t4~ Za.c.i Lity as d esca ibzJ 6.5.1.4.5 A safety evaluation an subsequent review that conclude that the subject action involves a change

'n the Final Safety Analysis Report shall be referred to the Nuclear Assessment Department for review in accordance with Specification 6.5.3.9, but implementation may proceed prior to the completion of that review.

6.5.1.4.6 The individual approving the procedure,

tests, or experiment or change thereto shall be other than those who prepared the safety evaluation or performed the safety review.

SHEARON HARRIS - UNIT 1 6"8 Amendment No.

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ADHINISTRATIVE CONTROLS 6.5.2 PLANT NUCLEAR SAFETY COMMITTEE (PNSC)

FUNCTION RN 6.5.2.1 The PNSC shaLL function to advise the Plant General Manager on all matters related to nuclear safety.

COMPOSITION 6.5.2.2 The PNSC shall be composed of the:

Cha irman'.

Member.'ember.'ember:

Hember.'ember'.

Member.'4l.efe~

em Plant General Manager Manager - Operations Manager Technical Support Manager Maintenance Manager " Environmental and Radiation Control Manager - Plant Programs and Procedures Mana er Re ulator Com liance 6.5.2.3 The Chairman may designate in writing other regular members who may serve as Acting Chairman of PNSC meetings.

All alternate members shall be appointed in writing by the PNSC Chairman.

Alternates shall be designated for specific regular PNSC members and,shall have expertise in the same general area as the regular member they represent.

No more than two alternates shall participate as voting members in PNSC activities at any one time.

HEETING FRE UENCY 6.5.2.4 The PNSC shall meet at least once per calendar month and as convened by the PNSC Chairman or his designated alternate.

The PNSC must meet in session to perform its function under these Technical Specifications.

gUORUH 6.5.2.5 The quorum of the PNSC necessary for the performance of the PNSC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.2.6 The PNSC shall be responsible for:

a.

Review of proposed procedures or changes thereto that have been initially determined to constitute an unreviewed safety question or involve an unreviewed change to the Technical Specifications>

SHEARON HARRIS UNIT 1

6-9 Amendment No.

P6

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued' bo Review of all proposed tests and experiments that affect nuclear safety and that have been initially determined to appear to consti-tute an unreviewed safety question or involve an unreviewed change to'he Technical Specifications>

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Review of all proposed changes to Appendix "A" Technical Specifications; d ~

Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety and that have been initially determined to appear to constitute an unreviewed safety question as defined in 10 CFR 50.59 or involve a change to the Technical Specifications; e.

Investigation of all.violations of the Technical Specifications, including the preparation and forwarding of reports covering. evalua-tion and recommendations to prevent recurrence, to the Vice President - Harris Nuclear Project and to the Manager Nuclear Assessment Department; f.

Review of all REPORTABLE EVENTS; go Review of unit operations to detect potential hazards to nuclear safety',

h.

Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant General Manager or the Manager Nuclear Assessment Department; 1 ~

Review of the Security Plan; Review of the Emergency

Plan, k.

Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recorrmendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President Harris Nuclear Project' 1

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Review, prior to implementation, of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, the Radwaste Treatment

Systems, and the Technical Specification Equipment List Program.

6.5.2.7 The PNSC shall:

a.

Render determinations in writing with regard to whether or not each item considered under Specification 6.5.2.6a.

through e. constitutes an unreviewed safety question; and SHEARON HARRIS. - UNIT 1 6"10 Amendment No.

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ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) b.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President "

Harris Nuclear Project and the Manager - Nuclear Assessment Department of disagreement between the PNSC and the Plant General Manager.

However, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

RECORDS 6'.2.8 The PNSC shall maintain written minutes of each PNSC meeting that, at a minimum, document the results of all PNSC activities performed under the responsibility provisions of these Technicah Specifications.

Copies shall be provided to the Vice President Harris Nuclear Project and the Manager-Npclear Assessment Department.

6.5 '

NUCLEAR ASSESSMENT DEPARTMENT INDEPENDENT REVIEW PROGRAM FUNCTION slav i%icake 6.5 '.1 The Nuclear Assessment Department shall function to provide independent review of plant changes,

tests, and procedures; verify that REPORTABLE EVENTS are investigated in a timely manner and corrected in a manner that reduces the probability of recurrence of such eventsR and detect trends that may not be apparent to a day"to-day observer.

OROANTZATION 6.5.3.2 The individuals assigned responsibility for independent reviews shall be technically qualified in a specified technical discipline or disciplines.

These individuals shall collectively have the experience and competence required to review activities in the following areas:

a.

Nuclear power plant operations, b.

Nuclear engineering, c.

Chemistry and radiochemistry, d.

Metallurgy, 7 Instrumentation and control, p Radiological safety, h Mechanical and electrical engineering,

'h.

t. Administrative controls,

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LOther appropriate fields associated with the unique characteristics.

SHEARON HARRIS UNIT 1

6-11 Amendment No.

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ADMINISTRATIVE CONTROLS ORGANIZATION (Continued)

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>~ Ll< I4 6.5.3.3 The Manager Nuclear shall have a

shall have a minimum of 10 years'elated experience, of which a minimum of 5

years shall be in the operation and/or design of nuclear power plants.

6.5.3.4 The independent safety review program reviewers shall each have a

degree in an engineering or related field or equivalent and, in addition, shall have a minimum of 5 years'elated experience.

6.5 '.5 An individual may possess competence in more than one specialty arear'f sufficient expertise is not available within the Nuclear Assessment Department, competent individuals from other Carolina Power

& Light Company organizations or outside consultants shall be utilized in performing independent reviews and investigations.

6.5.3.6 t

individuals, qualified as discussed in Specifica-tion 6.5.3.2 above shall review

'bmitted under the requirements of Sp

'fication 6 5

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6.5.3.7 Independent safety reviews shall be performed by individuals not directly involved with the activity under review or responsible for the activity under review.

6.5.3.8 The Nuclear Assessment Department independent safety review program shall be conducted in accordance with written, approved procedures.

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.3.9 The Nuclear Assessment Department shall perform reviews of the foll ing.

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'tten safety evaluations for all procedures and programs required by cification 6.8 and other procedures that affect nuclear safety and cha s thereto, and proposed tests or experiments and proposed modificatio

, any of which constitute a change to the Final Safety Analysis Repor Implementation may proceed prior to completion of the revi ew; b.

All procedures and progr s required by Specification 6 '

and other procedures that affect nucl safety and changes thereto that con-stitute an unreviewed safety q

tion as defined in Paragraph 50.59 of 10 CFR Part 50 or involve a cha e to the Technical Specifications; C ~

All proposed tests or experiments that const'te an unreviewed safety question as defined in Paragraph 50.59 o

10 CFR Part 50 or involve a change to the Technical Specifications p

or to implemen-tation',

do All proposed changes to the Technical Specifications and Ope ting License; SHEARON HARRIS - UNIT 1

6-12 Amendment No.

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6.5.3.6 The documents submitted under 6.5.3.9 shall be reviewed by individuals meeting the requirements of 6.5.3.2 and 6.5.3.4 to ensure disciplines are encompassed.

ADMINISTRATIVE CONTROLS REVIEW (Continued) e.

Violations, which require written notification to the Commission, of applicable

codes, regulations,

orders, Technical Specifications, license requirements, internal procedures or instructions having nuclear safety significance, significant operating abnormalities or deviations from normal and expected performance of plant safety-related structures,

systems, or components; f.

11 REPORTABLE EVENTS; g.

All roposed modifications that constitute an unreviewed safety quest on as defined in Paragraph 50.59 of 10 CFR Part 50 or involve a chan to the Technical Specifications; h.

Any other tter involving safe operation of the nuclear power plant that the Ma ger - Nuclear Assessment Department deems appropriate for considera ion or which is referred to the Manager Nuclear Assessment Dep tment by the onsite operating organization or other functional organ'tional units within Carolina Power

& Light Company',

i.

All recognized indica ions of an unanticipated deficiency in some aspect of design or op ation of structures,

systems, or components that could affect nuclea safety; and j.

Reports and minutes of the SC.

6.5.3.10 Review of items considered unde Specification 6.5.3.9.e, h and j above shall include the results of any inv tigations made and the recommenda-tions resulting from these investigations to revent or reduce the probability of recurrence of the event.

RECORDS 6.5.3.11 Records of Nuclear Assessment Department r views performed under Specification 6.5.3.9, including recommendations and c ncerns, shall be prepared and distributed as indicated below:

a.

Copies of documented reviews shall be retained in the NAD files.

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Recommendations and concerns Manager and Vice President-of completion of the review.

encompassed by Specification General Manager and the Vice every other month.

shall be submitted to t e Plant General Harris Nuclear Project wx hin 14 days A report summarizing the eviews 6.5.3.9 shall be provided to the Plant President - Har'ris Nuclear Pr ect C ~

A summation of recommendations and concerns of the Nuclear Assessment Department shall be submitted to the Chairman/Presiden and Chief Executive Officer and other appropriate senior managemen personnel at least eve'ry other month.

SHEARON HARRIS - UNIT 1

6"13 Amendment No. Pg

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4 REVIEW 6.5.3.9 The Nuclear Assessment Department shall perform reviews of the following:

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,d-Written safety evaluations of significant changes in the facility as described in the Safety Analysis

Report, significant changes in procedures as described in the Safety Analysis

Report, and significant tests or experiments not described in the Safety Analysis Report which are completed without prior NRC approval under the provisions of 10CFR50.59(a)(1).

These reviews are to verify that such changes,

tests, or experiments do not involve a change in the Technical Specifications or an unreviewed safety question as defined in 10CFR50.59(a)(2).

These reviews may be conducted after appropriate management

approval, and implementation may proceed prior to completion of the review.

Proposed changes in procedures required by these Technical Specifications, proposed changes in the facility, or proposed tests or experiments, any of which involve a change in the Technical Specifications or an unreviewed safety question pursuant to 10CFR50.59(c) prior to implementation.

Proposed changes to the Technical Specifications or this Operating License prior to implementation.

Violations, deviations and reportable

events, which require reporting to the NRC in writing, such as:

1)

Violations of applicable

codes, regulations,

orders, technical specifications, license requirements or internal procedures or instructions having safety significance, 2)

Significant operating abnormalities or deviations from normal or expected performance of plant safety-related structures,

systems, or components, and e.

3)

REPORTABLE EVENTS, as specified in section 50.73 of

10CFR50, which require reporting to the NRC in writing.

Any other matter involving safe operation of the nuclear power plant that the Manager Nuclear Assessment'epartment, deems appropriate for consideration or which is referred to the Manager Nuclear Assessment Department, by the on-site operating organization, Plant Nuclear Safety Committee (PNSC) or by other functional organizational units within Carolina Power

& Light Company.

RECORDS 6.5.3.10 Results of Nuclear Assessment Department independent safety reviews shall be documented and retained.

6.5.3.11 Potentially adverse conditions shall be submitted in accordance with the corrective action program.

6.5.3.12 A

briefing of the Nuclear Assessment Department activities, along with any potential issues and recommendations shall be presented to the Executive Vice President Power Supply and Senior Vice President Nuclear Generation Group on an approximately bimonthly frequency.

Copies of this presentation shall be provided to the Vice President Brunswick Nuclear

Project, General Manager Brunswick

Plant, and others as appropriate.

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C ADMINISTRATIVE CONTROLS A ssc,ss %e ~7 6.5.4 NUCLEAR ASSESSMENT DEPARTMENT h89+7 PROGRAM RepLcxce. elJI Ire sactiotJ lhlf (o,5. l

+N~<4J 5.4.1 Audits of unit activities shall be performed by the Nuclear As ssment Department.

These audits shall encompass:

a The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions, at least once per 12 months; b.

Th training, qualifications, and performance as a group, of the enti e unit staff, at least once 'per 12 months; c.

The res ts of actions taken to correct deficiencies occurring in unit equi ent, structures,

systems, or method of operation that affect nucl ar safety, at least once per 6 months',

d.

The performanc of activities required by the Operational Quality Assurance Progra to meet the criteria of Appendix B, 10 CFR Part 50, at least nce per 24 months; e.

The fire protection p ogranmatic controls including the implementing procedures, at least on e per 24 months, by qualified licensee QA personnel; f.

The Radiological Environment 1 Monitoring Program and the results thereof, at least once per 12 onths; g.

The OFFSITE DOSE CALCULATION MAN L and implementing procedures, at least once per 24 months; h.

The PROCESS CONTROL PROGRAM and implem ting procedures for processing and packaging of radioactive

astes, at least once per 24 months; i.

The performance of activities required by'the Quality Assurance Program for effluent and environmental monitor g, at least once per 12 months; j.

The Emergency Plan and implementing procedures, at ast once per 12 months; k.

The Security Plan and implementing procedures, at least ce per 12 months; and 1.

Any other area of unit operation considered appropriate by th Nuclear Assessment Department or the Vice President - Harris Nu ear Project.

6.5.4.2 Personnel performing the quality assurance audits shall have access to the plant operating records.

SHEARON HARRIS - UNIT 1

6-14 Amendment No. 2g

ADMINISTRATIVE CONTROLS

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CORDS 6.5.4.

Records of audits shall be prepared and retained.

6.5.4.4 dit reports encompassed by Specification 6.5.4.1 shall be

prepared, ap oved by the Manager Nuclear Assessment Department, and forwarded, with'0 days after completion of the audit, to the Executive Vice President " Power upply, Senior Vice President Nuclear Generation, Vice President - Harris lear Project, Plant General

Manager, and the management positions responsible r the areas audited.

AUTHORITY 6.5.4.5 The Manager Nuclear sessment Department shall be responsible for the following:

a.

Administering the Nuclear Asse ment Department Audit Program.

b.

Approval of the individuals select to conduct quality assurance audits.

6.5.4.6 Audit personnel shall be independent of th area audited.

6.5.4.7 Selection of personnel for auditing assignments hall be based on experience or training that establishes that their qualifica ions are commen-surate with the complexity or special nature of the activities o be audited.

In selecting audit personnel, consideration shall be given to sp ial abilities, specialized technical training, prior pertinent experien personal characteristics, and education.

6.5.4.8 Qualified outside consultants, or other individuals independent om those personnel directly involved in plant operation, shall be used to augmen the audit t'earns when necessary.

6.5.5 OUTSIDE AGENCY INSPECTION AND AUDIT PROGRAM

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,oP FSP R 6.5.5.1 An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months using either qualified offsite licensee personnel or an outside fire protection firm.

6.5.5.2 An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at inter-vals no greater than 36 months'.5.5.3 Copies of the audit reports and responses to them shall be forwarded to the Vice President - Harris Nuclear Project and the Manager Nuclear Assessment Department.

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

SHEARON HARRIS UNIT 1

6"15 Amendment No.

6.5.4 NUCLEAR ASSESSMENT DEPARTMENT ASSESSMENT PROGRAM The Nuclear Assessment Department is responsible for conducting independent assessments of functions/areas affecting nuclear safety, quality and reliability.

This program is described in the FSAR, Section 17.3.3.3.

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ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued)

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

6.10.3 The following records shall be x'etained for the duration of the unit Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report; bo Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories>

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Records of radiation exposure for all individuals entering radiation 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; f.

Records of reactor tests and experiments; Records of training and qualification for current members of the unit staff; h.

Records of inservice inspections performed pursuant to. these Technical Specifications; 1 ~

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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 meetings of the PNSC>

Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records; m.

Records of secondary water sampling and water quality>

n.

Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later data.

This should include procedures SHEARON HARRIS - VNIT 1

6-25 Amendment No.

AOMINISiiATIVE CONTROLS RECORO RETENTION Continued) effective at specified times and gA records showing that these procedures were followed; and o.

Records of facility radiation and contamination surveys.

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+orcla) 6.11 RAOIATION PROTECTION PROGRAM 6.11-1 Procedures for personnel radiation protection shall ba prepared consistent with the requirements of "10 CFR Part 20 and shall be approved, maintained, and adhered to for al.l oper ations involving personnel radiation exposure.

)g 6.12 HIGH RAOIATION AREA 6.12-1 Pursuant to Paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the "control device" or "alarm signal" required by Paragraph 20.203(c),

each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation cwork Permit (RMP).

Individuals qualified in radiation protection procedures (e.g., Health Physics Technicians) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, pro-vided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of tha following:

a.

A radiation monitoring devica that continuously indicates the radiation dose rata in the area; or A radiation monitoring device that continuously integrates the radiation dose rata in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made attar the dose rate levels in the area have been estab-lished and personnel have been made knowledgeable of them; or c.

An individual qualified in radiation protection,procedures, with a radiation dose rate monitoring device, who is responsible for pro-viding positive control over the activities within the area and who sha11 perform periodic radiation surveillance at the frequency specified by the Radiation Control Supervisor in the RWP.

6.12.2 In addiXion to the requirements of Specification 6.12.1, accessible areas with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation panetrates, shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift Foreman on duty SHEARON HARRIS - UNIT 1 6-26

6.10.3 p.

Records of independent reviews performed by the Nuclear Assessment Department.