ML18009A786

Proposed Tech Specs Revising Section 6.0, Administrative Controls to Reflect Changes in Organizational Structure

ML18009A786
Person / Time
Site:	Harris
Issue date:	01/15/1991
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18009A784	List: ML18009A783 ML18009A786
References
NUDOCS 9101230341
Download: ML18009A786 (17)

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 ORGANIZATION CHANGES TECHNICAL S CIFIC ION P GE 9101230341 910115

- PDR ADOCK 05000400 P PDR

AOMINISTRATIVE CONTROLS PRo3 ECT S$ KSSm ~ S~z~M

6. 2. 3 %N N~tCT FUNCTIQR PA Secor'~

6.2.3.1 The GNS-Ue& shall function to examine unit operating characteristics, NRC issuances, industry advisories (including information forwarded by INPO from their evaluation of all industry LERs), and other sources of unit design and operating experience information, including units of similar design, which may.indicate areas for improving unit safety. The GHS-UeH." shall make detailed difications, maintenance

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recommendations for revised procedures, equipment activities, operations activities, or other appropriate levels of management, up to and incl ding the Oaaeaeeaaa-Respect, i 1'eeessery.

mean of

~r improving unit safety, to Vice President-

'1 Pow<~ /~<ply pp gg~$ )'Or@'OMPOSITION 6.2.3.2 engineers Tl pp N~

located s8c+csa on. site.

I ~dudw Each shall have a 1 <<i, baccalaureate Ch*

degree d,

in engineer ing or related science and at least 2 years professional level experience in his field, at least 1 year of which experience shall be in the nuclear field.

RESPONSIBILITIES Ph SCckioP 6.2.3.3 The EN~rHt shall be responsible for maintaining surveillance of unit activities to provide independent verification" that these activities are performed correctly and that human errors are reduced as much as practical.

RECOROS Ph Sech'~<

6.2. 3.4 Records of activities performed by the 6N~n+t." shall be prepared, maintained, and forwarded each calendar month to the Manager Nuclear ~ety Q ssessweW f)~pprf aeef 6.2. 4 SHIFT TECHNICAL AQVISOR 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, The Shift and plant analysis with regard to the safe operation of the unit.

equivalent in a scien-Technical Advisor shall have a baccalaureate degree or tific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients instrumentation and accidents, and in unit design and layout, including the capabilities of and controls in the control room.

6.3 Qeleted "Not responsible for sign-off function.

SHEARON HARRIS - UNIT 1 6-6

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ADMINISTRATIV NTROLS uali fied Safet Reviewers Continued These individuals shall have a baccala'ureate =degree in an engineering or related field or equivalent, and 2 years of related experience. Such designa-tion shall include the disciplines or procedure categories for which each indi-

.vidual is qualified. gualified individuals or groups not on the plant staff may be relied upon to perform safety reviews General Manager.

if so designated by the Plant 6.5. 1.4 Safet Evaluations and A rovals 6.5.1.4. 1 The safety evaluation prepared in accordance with Specification 6.5. l. 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 unr eviewed 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.

n 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.

A safety evaluation and subsequent review that conclude that the '.5.1.4.3 subject action may involve an unreviewed safety question, a change to the Tech-nical Specifications, or a change to the Operating License, will be referred

~i 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 unr eviewed 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 f i y I I II t * ~i S fication 6.5.3.9. A5$ 6Q~f Qep<~ca+

6.5. 1.4.4 If a safety evaluation and subsequent review conclude that the sub-ject 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 individ-ual approving 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; 6.5.1.4.5. A safety evaluation and subsequent review that conclude that the referred to the Bm'piete Nuclear 'or subject action involves a change in the Final Safety Analysis Report shall be review in accordance with Specification 6.5.3.9, but implem tation may proceed prior to the completion of that review.

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6.5. 1.4.6 The individual approving the procedure, test, 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. 3

AOMINISTRATIYE C ROLS PLANT NUCLEAR SAFETY COMMITTEE PNSC FUNCTION 6.5.2.L The PNSC shall function ta advise the Plant General Manager on all matters related to nuclear safety.

COMPOSITION 6.5.2. 2 The PNSC shall be composed of the:

fAAAA5cv'.5.2Chairman: Plant General Manager

'ember: Manager Operations Member: Manager Technical Support Member: Manager Maintenance Member: Manager Environmental and Radfatfan Control ember: Plant Programs and Procedures Member:

Member:,

'egulatory

~e4er Compliance gA/gC-Harris Plant IHanayer.

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.

MEETING FREQUENCY 6.5.2-4 The PNSC shall meet at least once per calenda~ month and as canvened by the PNSC Chairman or 4fs designated alternate. The PNSC suit meet fa session to'erform its function under these Technical Specifications.-

OUONUN 6.5.2.5 The quorum of the PNSC necessary for the performance of the PNSC responsibility and authority provisfans of these Technical Specifications shall consist of the Chairman dr hfs 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 fnitfally determined to constitute an unrevfewed safety question or involve an unrevfewed change to the Technical Specifications; SHEARON HARRIS UNIT L 6-9

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AOMINISTRATIVE CONTROLS RESPONSIBILITIES Contfnued

b. 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 the Technical Specifications;

c. 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 reparts covering evalua-tion and recommendations ta prevent recurrence, to the Vice Presfdent-Harris Nuclear Pro)ect and to the Manager Quate Nuclear 4afe4y-.

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Revfew of all REPORTABLE EVENTS;

g. Revfew of unit operations to detect potentfal hazards to nuclear safety;

h. Performance of special reviews, investfgations, or analyses and reports thereon as requested by the Plant General Manager or the Manager-C~~a4'o Nuclear Review of the Security Plan; Review of'hi Emergency Plan;

k. Review of any accidental, unpIanned, or uncontrolled radfoactfve release fncludfng the preparation of reports covering evaluation, recoaeandatfons, and disposition of the corrective action to prevent recurrence and the forwardfng of these reports ta the Vice President-Harris Nuclear Pra]ect and the Manager-Nuclear hsscane~f- +~~A~

Review, prfar to fmplementatfon, of changes ta the PROCESS CONTROL

. PROGRAM, the OFFSITE OOSE CALCULATION MANUAL, the Radwaste Treatment Systems, and the Technfcal Specfffcatfon Equipment Lfst Program.

6.5.2.7 The PNSC shall:

Render deterafnatfons fn writing with regard to whether or not each flea cansfdiref under Specfffcatfon 6.5.2.6a. through e. constftutes an unrevfewect safety question; and SHEARON HARRIS - UNIT 1

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AOMINISTRATIVE OLS 1

RESPONSIBILITIES Continued QgPN,F flit(Il

b. Provide written notiffcation within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to e Vfha President- *

'Harris Nuclear Project and the Manage Nuclear I S~+em of dfsagreement between the PNSC and the Plant General Manager.

However, the Plant General Manager shall have responsibili y for resolution of such disagreements pursuant to Speciffcatfon 6.L.L.

RRCOROS 6.5.2.8 The PNSC shall maintafn written mfnutes of each PNSC meeting that, at a minimum, document the results of a11 PHSC actfvftfas performed under the provisfons of these Technical Spacffications. Copies shall be 'esponsfbflfty provided to the Vice" President-Harrfs Nuclear Prospect and the Manage Nuclear 6.5.3 ~~~

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T FUNCTION ThcIV.r:~lawn AsssssMGa+

6.5.3.L Oepartment shall function to provide independent review of plant changes, tests, and procedures; verify that REPORTABLE,EVENTS are in--

vestigated in a timely manner and corrected fn a manner that reduces the proba-bflfty of recurrence of such events; and detect trends that may not be apparent to a day-to-day observer.

ORGANIZATION 6-5.3.2 The fndfvfduals assigned responsfbflfty for independent review shall be technically qualf ffed fn a specfffed technfcal dfscfpl inc or dfscfplines.

These fndfvfduals shall collectively have the experfence and competence requfred to revfas actfvftfes fn the following areas:

a.. Huclear power plant operations,

b. Nuclear engf neerfng, c.

d.

e.

f.

h.,:

-

Metal 1urgy,

• Chemfstry and radfochemfstry, Instrumentatf on and control, Radf ologf cal safety, g.,- Mechanfcal and electrfcal engfneerfng, Admf nf stratf ve controls,

f. '-- gualfty assurance practfces, g..;- Nondestructfve testing, and

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Other'pproprfate fields assocfated with the unique characterfstfcs.

SHEARCN HARRIS UNIT L

AOHIHISTRATIVE C ORGANIZATION 6.5.i.3 Yh 1I g ~

OLS Continued degree in an engineering or related mum of 10 years'elated experience, t

of the operation and/or design of nuclear power plants.

'6.5.3.4 The independent baccalaureate degree in

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A Sic field ss~rt' and, which an engineering or related a

in gpss minimum r~W addition, t1'h of 5 shall have a mini-years shall be in safety review. program reviewers shall each have a field or equivalent and, in addition, shall have a minimum of 5 years'elated experience.

jl sess~~ Dcf 6.5.3.5 An individual may possess competence in more than one special area.

If sufficient expertise -is not available within the 4~~4@ Nuclear

$ ~$ en; competent individuals from other Carolina Power 4 Light Company organizations or outside consultants shall be utilized in performing .indepen-dent'eviews and investigations.

6.5.3.6 At least three individuals, q~alified as discussed in Specifica-tion 6.5.3.2 above shall review each item submitted under the requirements of Specification 6.5.3.9.

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.

see s~W b 6.5.3.8 The C~em& Nuclear independent safety review pro-gram shall be conducted in accordance with written, approved procedures.

REVEBf Assess~<+ h~~~

6.8.3.9 Th N e M N shall perform reviews of the following:

a. Written safety evaluations for all procedures and programs required by Specification 6.8 and other procedures that affect nuclear safety and changes thereto, and propoied tests or experiments and proposed modi-fications, any of which constitute a change to the Final Safety Analysis Report. Implementation may proceed prior to completion of the review;

b. All procedures and programs required by Specification 6.8 and other procedures that affect nuclear safety and changes thereto that con-

', stitute an unreviewed safety question as defined in Paragraph 50.59 of 10 CFR Part-50 or involve a change to the Technical Specifications; C. All proposed tests or experiments that constitute an unreviewed safety question as defined in Paragraph 50.59 of 10 CFR Part 50 or 4

involve a chango to the Technical Specifications prior to implemen-

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tation; All proposed changes to the Technical Specifications and Operating License; SHEARGN HARRIS - UND 1

AOHINISTRATIYE REYI Bl Co'ntinued

e. Violations, which require written notit'fcatfon to the Commission, of applicable codes, regulatfons, orders, Technical Specftfcatfons, license requfreaents, fnternal, proc'edures or instructions having nuclear safety signii'fcance, sfgnfffcant operating abnormalities or deviations from normal and expected performance ot'lant safety-related structures, systems, or components;

.f. All REPORTABLE EVENTS;

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All proposed modfl'fcatfons that constitute an unrevfewed safety ques-tion as deffned fn Paragraph 50.59 of 10 CFR Part 50 or involve a .

change to the Technical Specfffcatfons; g~

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h. Any other matter fnvolving safe opa.ation of the nuc1ear po~er plant g ""*I deems appropr fate I' f I* I I Nuclear . by the onsite oper atfng organfzation or other

~elcf o al organfzatfonal units within Carolina Power 4 t.ight ssas~e~f'I Company; All recognized fndicatfons of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could aff'ect nuclear safety; and Reports and mfnutes of the PNSC.

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6.5.3.10 Review of ftams consfdered under Specfffcatfon 6.5.3.9.e, h and shall include the results ot'ny investigations made and the recaaeenda-j 'bove tfons resultfng f'res these fnvestfgatfons to prevent or reduce the probability of recurrence of the event.

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5.5.3.33 I ~ IgM recommendatf ons and concerns, h*t sha11 be prepared and I .I I tg df stributed as indicated

~f below:

a. -

Copies of documented revfews sha11 be retafned fn the ASS ffles.

h. I I llh 'MM II gl I Nanager and Vfca Presfdent&arrfs Nuclear Prospect wfthfn 14 days of':

coap1etfon of the review. A report semarfzfng the reviews encom-

.".'assed by Speci tfcatfon 6.5 3.9 sha11 be provided to the Plant General

. Manager and the Vice President-Harrfs Nuclear Pro5ect every other month.

. c. A. suenatfon of recomendatfons and concerns of the Corporate Nuclear hal1 be subeftted to the Chafnun/Presfdent and Chfef Executive Offfcer and other appropriate senior management personnel at least every other month.

SHEARCN HARRIS NIT 1

AOHINISTRATIVE C OLS h ue,lm~ Assc5$ &ch+' a~c<+h4'Ol7 f ICo ~A 6.5;4 f

AUOITS AAII Adl I I *III A!I A 5 I dby b guckav As$ es$ mc~+

Oepartment. These audi ts.

shall encompass:

a. The conformance of unit operation Co'provisions contained wfthin the Technical Specifications and applicable license conditions, at least once per IZ months;

'. The training, qualifications, and'performance as entire unit staff, at least once per 12 months; a group, of the

c. The results of actions taken to correct deficiencies accurr'fng in unit equipment, structures, systems, or method of operation hat affect nuclear safety, at least once per 6 manths; d..; The performance of activities required by the Operational quality Assurance Program to meet the critaria of Appendix B, 10 CFR Part 50,

'at least once per 24 months;

e. The. fire protection programmatic controls including the implementing procedures, at least once per 24 months, by-qualified licensee gA>>

personnel;

f. The Radfological Environmental Honftorfng Pragram and the

'.

results-thereof, at least once per LZ manths;

, .go The QFFSITE 00SE CALCUULTION MANUAL and fmplementfng procedures, at least once per 24 months;

h. The PROCESS CONTROL PRGQRAH and fmplementfng procedures for processing and packaging of radfoactfve wastes, at least once per 24 months; The performance of activftfes required by the quality Assurance effluent and environmental monitoring, at least ance per

'Z Prograa for months; The Emergency Plan. and implementing procedures, at least ance per L?

I' months.

k. ', The Security Plan and fmplementfng procedures, at least once per LZ aonths; and

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Any other area of unft 'operation consfdered appropriate by the 5*1 Al>> ~ >> I II

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+~a~.;I I Pxoject. Assess~+

6;5.4.2 Personnel performing the, quality assurance audits ihall have access to the plant operating records.

SHEARQN HARRIS UNO 1

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ADMINISTRATIVE OLS RECORDS C

6.5.4.3 Records of audits shall be prepared and retained.

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6.5.4.4 Audit reports encompas'sed by Specfffcatfon.6.5.4.1 shall be prepared, approved by the Manage , and forwarded, within 30 days after Power Supply completion of the audit, to the W~ Executfve Vice President-Senior Vice President-Nuclear

,

Generation, Vice Presfdent-Harrfi Nuclear Pro)ect,

, Plant General Manager, and the management positions responsible for the areas audited.

AUTHORITY gq~(gq) g sseu'~elf D8p~v'tm~~

6.5.4.5 The Manager shall be responsible for the.'following:

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a. Admf nf ster ing the Audi t P.rogram.

b. Approval of the individuals selected to conduct quality assurance audits.

6.5.4.6 =

Audft personnel shall be independent of the area audited.

6.5.4.7 Selection of personnel for auditing assignments shall be based on experience or training that establishes that their qualfffcatfons are coaeen-surate with the complexity or special nature of the actfvftfes to be audited.

In selecting audft personnel, consfderatfon shall be given to special abilfties,.

specfalfzed technical training, prior pertinent experience, personal character fstics, and educatfon.

6.5.4.8 gualfffed outside consultants, or other fndfvfduals independent. from those personnel'dfrectly fnvoTved fn pTant operatfon, shall be used to augment the audit teams when neceisary.

6.5.5 OUTSIDE AGENCY INSPECTION'ND AUDIT PROGRAM

~

6.5.5.1 An fndependint ffre protection and loss prevention inspection and audit shall be performed at least once per ZZ months usfng either qualiffed offsfte licensee personnel or an outsfde fire protectfon firn.

6.5.5.2 An fnspectfon and audft of the ffre protection and Toss prevention prograa shall be perforned by an outsfde qualfffed ffre consultant at'nter vals no greater than 36 Nonths.

lf'.5.5.3 Copfes of the- audft reports and responses to thea shaIT be forwarded Vf P f i *1 P 5 th N h4dwv, /sSesswen+

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6. 6 REPQRTAELE EVENT ACTION 6.6.1 The foTIowfng actions shall be taken for REPORTABLE EVENTS:

'

SHEARON HARRIS NIT 1

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AOHINISTRATIVE C OLS REPORTABLE EVENT ACTION Continued t

a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the PNSC, and the results of this review shall be submitted to the Hanager 6orpe~e Nuclear and the Vice President-Harrfs Nuclear Project.

Asscs5~<

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

notified p+~~

a.

~

The II 1 shall NRC possible and in he P i:

Operations Center shall he all notified cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

~ th II I within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; cw 8 by telephone as soon as The Vice Presfden-Harris

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b. A Safety Limit Violation Report shall he prepared. The report shall be reviewed by the PNSC. This report shall describe: (1) applicable circumstances preceding the violation, (2) effects of the violation

~,

upon facility components, systens, or structures, and (3) corrective action taken to prevent recurrence;

c. The Safety Limit Violation Report shall be submitted, within 14 days of the violation, to the Commission, the Manager O~eCe Nuclear Ass~~~n~

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d. Operation of the unit shall not be resumed until authorized by the Coaefssfon.

6.8 PRQCEQURES ANQ PROGRAMS 6.8.1 Written procedures shall be established,-fmplemented, and maintained covering the activities referenced below:

a. The applfcable procedures recoaeanded fn Appendix A of Regulatory Guide 1.33, Revision 2, February 1978;

b. The emergency operating procedures required to fmplement the require-ments of NUREG-0737 and SuppIement 1 to NUREG-0737 as stated fn Generic Latter No. 82-33; c Security Plan fmpleaentatfon;

d. Emergency Plan implementation;

' 00 PROCESS CONTROL PROGRAM fmplementatfon; OFFSITE QQSK CALCULATION NNJAL fmpleaentatf on;

'SHEARQN'ARRIS - UND 1

AOHINISTRATIVE CONTROLS RECORO 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:

a., Records and drawing changes reflectfng 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; C. Records of radiation exposure for all individuals entering radiation control areas;

d. Records of gaseous and liquid radioactive materfal released to the environs ~

Records of transfent or operatfonal cycles for those unit components identified in Table 5.7-1; Records of reactor tests and experiments; Records of training and qualfficatfon for current members of the unit staff; Records of inservfce fnspectAon~serformed pursuant to these Technical f

Speci fcatf ons; Records of quality assurance activities required by the Corporate equal fty Assurance Program; 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 meetfngs of the PNSC and of the independent reviews per formed by the Compo~ Nuclear so cd'~ epa~cW~

'ecords of the service lives of all hydraulfc and mechanical snubbers

.. 'ervfce required by Specification 3.7.8 fncludfng the date at ~hich the lf fe coaeences and assocfated installation and maintenance records

'ecords of secondary water sampling and water quality; Records of analyses required by the Radiological Environmental Nonftorfng Prograa that would permit evaluation of the accuracy of

.the analysfs at a later date. This should tnclude procedures SHEARON HARRIS - UNIT 1 6-25