ML20155E708

Proposed Tech Spec Administrative Controls Sections 6.1-6.5, & Associated Figures,Changing Organization

ML20155E708
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Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	06/13/1988
From:	LONG ISLAND LIGHTING CO.
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ML20155E692	List: ML20155E708
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NUDOCS 8806160184
Download: ML20155E708 (12)

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INDEX ADMINISTRATIVE CONTROLS i

SECTION 6.1 RE S P O N S I B I LI TY.............................................. 6 - 1 6.2 O RG ANI ZAT I ON................................................ 6 - 1 6.2.1 NUCLEAR ORGANIZATION................................... 6-1 6.2.2 UNIT STAFF............................................. 6-2 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP................... 6-6 F UN CTI 0N............................................... 6 - 6 COM PO SITI ON............................................ 6 - 6 RESPONSIB1LITIES....................................... 6-6 RE C 0 RD S.....................................,.......... 6 - 6 6.2.4 SHIFT TECHNICAL ADVIS0R...........................'..... 6-6 i

6.3 UNIT STAFF QUALIFICATIONS................................... 6-6 6.4 TRAI N I N G.................................................... 6 - 7 6.5 REVIEV AND AUDIT............................................ 6-7 i

6.5.1 REVIEV 0F OPERATIONS COMMITTEE (R00)................... 6-7 F UN CT I ON............................................... 6 - 7 COMPOSITION............................................ 6-7 A LT ERN AT E S............................................. 6 - 7 MEETING FREQUENCY...................................... 6-7 0VORUM.................................................6-7 i

RESP 0NSIBILITIES....................................... 6-8 RE C 0 RD S................................................ 6 - 9 i

6.5.2 NUCLEAR REVIEV BOARD (NRB)............................. 6-9 i

F UN CT I ON............................................... 6 - 9 l

CO M P O S I TI ON............................................ 6 - 9 A LT ERNAT E S............................................. 6 - 9 i

CO N S U LT ANT S............................................ 6 - 10 l

MEETING FREQUENCY...................................... 6-10

'l Q U 0 RU M...,.............................................. 6 - 10 l

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SHOREHAM - UNIT 1 xix

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INDEX LIST OF FIGURES FIGURE PAGE 3.1.5-1 SODIUM PENTABORATE SOLUTION TEMPERATURE /

CONCENTRATION REQUIREMENTS.............'........

3/4 1-21 3.1.5-2 SODIUM PENTABORATE SOLUTION CONCENTRATION VS. NET TANK V0LUME.......................................

3/4 1-22 3.2.1-1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATF. (MAPLHGR) VS. AVERAGE PL5 NAP EXPOSURE, INITIAL CORE FUEL TYPE SCR233...........

3/4 2-2 3.2.1-2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VS. AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR183.....................

3/4 2-3 3.2.1-3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VS. AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR711.....................

3/4 2-4 3.2.3-1 MINIMUM CRITICAL POVER RATIO (MCPR) VERSUS t AT RATED FL0V.....................................

3/4 2 8 3.2.3-2 Kf FACT 0R.........................................

3/4 2-9 3.4.6.1-1 MINIMUM REACTOR "".SSEL METAL TEMPERATURE VS. REA CTOR VE S S E L PRE S S URE.......................

3/4 4-21 3.6.1.6-1 DRYVELL AND SUPPRESSION CHAMBER INTERNAL PRESSURES 3/4 6-10 3.6.2.1-1 PRESSURE DECAY VS. TIME DURING DRYVELL IN-SERVICE BYPASS TESTING (17.97 psia).......................

3/4 6-18 3.6.4 1 PRESSURE DECAY VS. TIME DURING DRYVELL IN-SERVICE BYPASS TESTING (15.97 psia)............

3/4 6-36 4.7.5-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST........

3/4 7-19 B 3/4 3-1 REACTOR VESSEL VATER LEVEL........................

B 3/4 3-8 B 3/4.4.6-1 FAST NEUTRON FLUENCE (E>MeV) AT 1/4 T AS A FUNCTION OF SERVICE LIFE..........................

B 3/4 4-8 5.1.1-1 EXCLUSION AREA....................................

5-3 5.1.2-1 LOV POPULATION Z0NF,...............................

5-4 5.1.3-1 SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS...........'...........

5-5 6.2.1-1 CORPORATE-NUCLEAR ORGANIZATION (DELETED)..........

6-4 6.2.2-1 UNIT ORGANIZATION (DELETED).......................

6-4 SHORERAM - UNIT 1 xxi

6.0 ADMINISTRATIVE CONTROLS 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 Vatch Engineer (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 Vice President - Nuclear Operations shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION 6.2.1 Nuclear Organization An organization shall be established for unit operation and corporate management. This organization shall include the positions for activities affecting the safety of the nuclear po er plant, 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 organizations positions.. These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions 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 SAR and updated in accordance with 10 CFR 50.71(e).

b.

The Vice President - Nuclear Operations shall have corporate t

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.

c.

The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities

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necessary for safe operation and maintenance of the plant.

1 d.

The ir;dividuals 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 i

organizational freedom to ensure their independence from operating pressures, i

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SHOREHAM - UNIT 1 6-1

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6.0 ADMINISTRATIVE CONTROLS UNIT STAFF 6.2.2 The station organization ahall be subject to the following a.

Each on duty shift shall be composed of at least the minimum shift crev composition shovn in Table 6.2.2-1; b.

At least one licensed Reacter 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 Operator shall be in the control room; c.

A Health Physics Technician

• shall be on site when fuel is in the reac'or; d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or licensed Senior Reactor Operator Limited to Fuel Bandling who has no other concurrent responsibilities curing this operation; e.

A site fire brigada of at least five members shall be maintained on site at all times *. The fire brigade shall not include the Vatch Engineer, the Shift Techniaal Advisor, nor the two other members of the minimum shift crev nece0sary for safe shutdovn of the unit and any personnel required for other essential functions during a fire emergency; and f.

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, health physicists, auxiliary operators, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine heavy use of overtime.

The objective shall be to have operating personnel vork a normal 8-hour day, 40-hour veek while the unit is operating.

Bovever, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdovn for refueling, major maintenance, or major unit modification, on a temporary basis the following guidelines shall be folloved:

1 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 /> strai,ght, 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 vork i

periods, including shift turnover time.

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• The Health Physics Technician and fire brigade composition may be less than the I

cinimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to cecommodate unexpected absence, provided immediate action is taken to fill the required positions.

SHOREHAM - UNIT 1 6-2

l 6.0 ADMINISTRATIVE CONTROLS 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 Plant Manager or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the i

deviation, controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

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SNRC-1465 Page 1 of 2 To License Change Application #14 1.0 Definition of Change In Technical Specification section 6.2.3.1 (last line) and 6.2.3.4 (next to last and last line) change title "Director, Quality Assurance, Safety and Compliance" to "Manager, Nuclear Quality Assurance Department".

In Technical Specification section 6.5.2.1 delete "Executive Vice President" and replace with "Vice President - Nuclear Operations".

In Technical Specification sections 6.5.2.8.g, 6.5.2.9.a, b, and c, delete "Executive Vice President" and add "Assistant Vice President - Nuclear Operations".

2.0 Reason for Change Effective July 1987, the position "Director, Quality Assurance, Safety and Compliance" was re-titled "Manager, Nuclear Quality Assurance Department".

This change has been reflected in the SNPS USAR revision 1 transmittal forwarded to the NRC in December 1987.

This License Change Application will achieve consistency within licensing documents.

Additionally, this License Application reflects the change in the Nuclear Review Board (NRB) reporting requirements from the Executive Vice President to the Vice President - Nuclear Operations, and the organizational interfacing of the Assis-tant Vice President - Nuclear Operations as a result of the i

realignment of Corporate Management responsibilities on January 1, 1988.

The NRC was informed of these organi-zational changes by SNRC-1403 and SNRC-1412 dated December 8, 1987 and January 28, 1988, respectively.

3.0 Basis For No Significant Hazards Finding In addition to the basic criteria of 10 CFR 50.92(c) addressed below, this amendment request falls within the guidance provided by the Commission (48 FR 14870) regarding examples of amendments that are not likely to involve signi-ficant hazards considerations.

Specifically, this proposed amendment is an "administrative change" to technical specifi-cations: for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature.

The proposed change does not involve a significant hazards consideration because operation of the Shoreham Nuclear Power Station - Unit 1 in accordance with this change would not:

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SNRC-1465 Page 2 of 2 (1) involve a significant increase in the probability or consequence of an accident previously evaluated.

This change merely corrects an inconsistency with other plant documents, and reflects organizational changes.

The change is administrative in nature and does not affect the operation of the p1. ant.

(2) create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed change is administrative in nature, and no physical alterations of plant configuration or changes to setpoints or operating parameters are proposed.

(3) involve a significant reduction in a margin of safety.

The proposed change is administrative in nature.

The realignment of Corporate Management responsibilities, and reporting requirements of the Nuclear Review Board ensures that the integrity of the Nuclear organization is protected and that, where required, the execution of oversight functions is maintained with functional independence from operating pressures.

4.0 Timing of Change Since this change is administrative in nature, LILCO requests that it become effective upon issuance.

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FIGURES 6.2.1-1 AND 6.2.2-1 HAVE BEEN DELETED.

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SHOREEAM - UNIT 1 6-4

ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION l

6.2.3.1 The ISEG shall function to examine un,it operating characteristics NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including. units of similar design, which may indicate areas for improving unit safety. The'ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance cetivities, operations activities or other means of improving unit safety to the Manager, Nucler.r Quality Assurance Department.

l COMPOSITION I

6.2.3.2 The ISEG shall be composed of at least five, dedicated multidisciplined, full-time engineers located on site.

Each shall have a bachelor's degree in engineering or related science, or equivalent, and at least 2 years professional cxperience in his field, at least 1 year of which experience shall be in the nuclear field.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be. responsible for maintaining surveillance of unit cetivities"to provide independent verification

• that these activities are i

performed correctly and that human errors are reduced as auch as practical.

RECORDS

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6.2.3.4 Records of activities performed by the ISEG shall be prepered, l

maintained, and forwarded each calendar month to the Manager, Nuclear Quality Assurance Department.

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

Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response

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and analysis of the unit for transients and accidents, and in unit design and

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layout, including the capabilities of instrumentation and controls in the control room.

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j 6.3 UNIT STAFF QUALIFICATIONS j

6.3.1 Rach member of the unit staff shall meet or exceed the miniaua ii i qualifications of ANSI N18.1-1971 for comparable positions and the supplemental rcquirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 2,

NRC letter to all licensees, except for the Health Physics Engineer who shall meet er exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Section A and C of ii of the March 28, 1980 NRC letter to all licensees.

1 Snot responsible for sign off function.

l SHORERAM - UNIT 1 6-6

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ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

Provide vritten 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 c.

President-Nuclear Operations and the Nuclear Review Board of disagreement between the ROC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

RECORDS 6.5.1.8 The. ROC Shall maintain vritten minutes of each ROC meeting that, at a minitum, document the results of all ROC activities performed under the responsibility provisions of these Technical Specificatior.s.

Copies shall be provided to the Vice President-ruelear Operations and the Nuclear Review Board.

6.5.2 NUCLEAR REVIEV BOARD (NRB)

F_ UNCTION 6.5.2.1 The NRB shall function to provide independent review and audit of designated activities in the areas of:

Nuclear power plant operations, a.

b.

, Nuclear engineering, Chemistry and radiochemistry, c.

d.

Metallurgy, Instrumentation and control, e.

f.

Radiological safety, Mechanical and electrical engineering, and g.

h.

Quality assurance practices The NRB shall report to and advise the Vice President-Nuclear Operations on those areas of responsibility in Specifications 6.5.2.7 and 6.5.2.8.

COMPOSITION 6.5.2.2 The NRB shall be composed of the permanent NRB Chairman and a minimum i'

of five permanent ?!RB members.

The chairman and all members of the NRB shall have qualifications that meet the requirements of Section 4.7 of ANSI /ANS 3.1-1978.

The membership shall include at least one individual from outside LILCO's or its contractors' organizations and at least one individual with substantial BVR operating experience.

The BVR operating experience may be provided by the individual who is from outside LILCO's or its contractors' organizations.

ALTERNATES 53 6.5.2.3.

All alternate members shall be appointed in writing by the NRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NRB activities at any one time.

SHOREHAN - UNIT 1 6-9

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ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of station activities shall be performed under the cognizance of the NRB. These audits shall encompass:

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

b. The performance, training and qualifications of the entire station staff at least once per 12 months;

c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months;

d. The performance of activities required by the Quality Assurance Program to meet the criteria 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 QA personnel;

f. The fire protection equipment and program implementation at ] east once per 12 months utilizing either a qualified offsite licensee fire protection engineer (s) or an outside independent fire protection consultant. An outside independent fire protection consultant shall be utilized at least every third years

g. Any other area of station operation considered appropriate by the NRB, Vice President-Nuclear Operations, or the Assistant Vice President-Nuclear Operations;

h. The radiological environmental monitoring program and the results thereof at least once per 12 months;

i. The or/SI?E DOSE CALCULATION MANUAL and implementing procedures at leae once per 24 months; and

f. The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive vastes at least once per 24 months;

k. The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months.

RECORDS 6.5.2.9 Records of NRB activities shall be prepared, approved, and distributed as indicated belev

a. Minutes of each NRB meeting shall be prepared, approved, and forwarded to the Vice President-Nuclear Operations and the Assistant Vice President-Nuclear Operations within 14 days following each meeting.

SHOREHAM - UNIT 1 6-11

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.WMINISTRATIVE CONTROLS RECORDS (Continued) b.

Reports of reviews encompassed by Specification 6.5.2.7 shall be prepared, approved, and forwarded to the Vice President-Nuclear Operations, and the Assistant Vice President-Nuclear Operations within 14 days following completion of the reviev.

c.

Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to the Vice President - Nuclear Operations, the Assistant Vice President-Nuclear Operations, and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

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

The Commission shall be notified and a report submitted pursuant to the a.

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

Each REPORTABLE EVENT shall be revieved by the ROC, and the results of this reviev shall be submitted to the NRB and the Vice President-Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the evert a safety Limit is violated:

The NRC Operations Center shall be notified by telephone as soon as a.

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 Vice President-Nuclear Operations and the NPB 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 ROC. 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.

i The Safetylimit Violation Report shall be submitted to the c.

Commission, the NRB, and the Vice President-Nuclear Operations within i

14 days of the violation, j

d.

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

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SBOREHAM UNIT 1 6-12

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