ML20012A910

Amend 61 to License NPF-38,changing Tech Specs by Revising Section 6 on Operator Qualification & Training to Reflect Current 10CFR55

ML20012A910
Person / Time
Site:	Waterford
Issue date:	02/21/1990
From:	Hebdon F Office of Nuclear Reactor Regulation
To:
Shared Package
ML20012A911	List: ML20012A910 ML20012A912
References
NUDOCS 9003120780
Download: ML20012A910 (11)

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UNITED STATES -

. :s; NUCLEAR REGULATORY COMMISSION

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- WASHINGTON, o.C 20555 L

LOUIS 1ANA. POWER AND LIGHT COMPANY DOCKET NO. 50-382

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WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. NPF-38 9

1.

The Nuclear Regulatory Comission (the Comission) has found that:.

A.

The applications for amendment by Louisiana-Power and Light' Company (the liunsee)- dated August;23 and October 16,1989, comply with the-standards and requirements of the Atomic Energy Act

> of -.1954, _as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The. facility will'o)erate in conformity with the application, the; provisions of tie Act, and the rules _and regulations of the

- Comission; C.

There is reasonable ~ assurance (1) that the activities authorized by this amendment can be conducted without. endangering the health and safety of the public, and-(ii) that cuch activities will be conducted in compliance with the Comission's regulations; D..

The issuance of this amendment will not be inimical to the-comon defense and security. or to the health and safety of the

-public; and--

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E.

The issuance of this amendment is in accordance with 10 CFR 1Part 51 of the Comission's regulations and all applicable

' requirements have been satisfied.

9003120780 900221 tPDR ADOCK 05000382_

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Accordingly, the license is amended by changes to the Technical Specifications:as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.

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NPF-38.is hereby amended.to read as follows:

(2)-TechnicalSpecifications'andEnvironmentalProtectionPlan

_The__ Technical Specifications contained in Appendix A, as revised through Amendment No. 61, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in'the license.

The licensee shall operate the facility in accordance with the Technical Specifications and-the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION t

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Frederickd.

on, Director-Project Directorate IV L:

Division of Reactor Projects - III, IV, V and Special Prdjects

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l' Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date-ofLIssuance: February 21, 1990 d

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ATTACHMENT-TO LICENSE AMENDMENT NO. 61 9:,;p TO FACILITY OPERATING LICENSE NO. NPF-38 14 DOCKET NO. 50-382.

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Replace the following pages of the Appendix A Technical Specifications dwithithe attached pages. The revised pages are, identified by Amendment

number and contain vertical lines indicating the areas of change. The

': corresponding overleaf pages are also provided to maintain document

-completeness..

f, Remove

' Insert 3/4 4-32:

3/4 4-32 I

6-2 6-2

.6 6-7

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' ADMINISTRATIVE CONTROLS:

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l6.3-UNITSTAFFQUALIFICATIONS 6.3.1' Each member'of the unit staff shall meet or exceed the minimum

~ qualifications.of_ ANSI /ANS 3.1-1978 except that:

L a.

'The Radiation Protection Superintendent shall meet or exceed the 4

minimum qualifications of Regulatory Guide 1.- 8, September 1975.

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b.

Personnel in.the Health Physics, Chemistry and Radweste Departments i

shall: meet or exceed the minimum qualifications'of ANSI N18.1-1971.

'The' licensed Operators and Senior Operators shall also meet or exceed c.

the minimum qualifications of 10 CFR Part 55.'

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.d.

Personnel in the Nuclear Quality Assurance Department, and other staff personnel who perform inspection, examination, and testing

~ functions, shall meet or exceed t.no minimum ganlifications of Regulatory Guide-1.58 - Rev.1, September 1980.

(Endorses ANSI N45.2.6-1978).

I 6.4. TRAINING L

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6.4.1. A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Manager-Nuclear and shall meet or exceed the requirements and recommendations of Section 5.2 of ANSI 3.1-1978 and 10 CFR Part 55.

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'6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW CO>NITTEE (PORC)

FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on:all matters related to nuclear safety.

COMPOSITION 6.5.1.2..The PORC shal1~be composed of the following members:

Assistant Plant Manager - Technical Services

' Assistant Plant Manager - Operations and Maintenance U.

Plant Engineering Superintendent Maintenance Superintendent-Operations Superintendent c'

- Radiation Protection Superintendent

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Management Knowledgeable-in Quality Assurance / Control

..Either of.the Assistant Plant Managers will be Chairman and the Plant Engineering Superintendent will be Vice Chnirman.

, WATERFORD - UNIT 3 6-7 Amendment No. 18, 0,61 J

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6. 5.1. 3 Manager will appoint a temporary Chairman.In the absence of t P

'be appointed in writing by the FORC Chairman All other alternate'eeimbers shall uJ asis; PORC activities:st any one time.

. MEETING FREQUENCY by the' PORC Chairman or his designated alternate.6.5.

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QUORUM-j responsibility and authority provisions of these T c

shall consist of the Chaiman or his designated alternate and three me including-alternates.-

RESPONSIBILITIES.

6. 5.1. 6 The PORC shall be respons*ble for the below ifsted activities.

PORC may delegate the performance of reviews but will asintain c The

.and responsibility for them,

. Review of.(1) a11 procedures required by Specification ~5 s.

thereto,2(2) all programs required by Specification 6.8 and cha thereto, and (3) any other proposed procedures or changes there.!

determined by the Plant Manager to affect nuclear safety.

b.

Review of all. proposed tests and experiments that affect nuclear safety.

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-Review of all proposed changes to Appendix "A" Technical Spec c.

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equipment that affect nuclear safety. Review of all propo Review of investigations of all violations of the Technical

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Specifications:incipding the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to th Plant Manager and to the Safety Review Committee, f.

Review of all REPORTA8LE EVENTS.

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$' ATERFORD'.- UNIT 3 5-8 3

AxtNpxntt No. la _

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• k ADMINISTRATIVE CONTROLS

__a 6.1 RESPONSIBILITY s

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.

5.1.2 The Shift Supervisor, or during his absence from the control room, a designated individual shall be responsible for the control room command func-i tion. A management directive to this effect signed by the Vice Presioent -

Nuclear, shal' be reissued to all station per,sonnel on an annual basis.

6.2 ORGANIZATION-6.2.1' 0FFSITE AND ONSITE ORGANIZATIONS p

i Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.

The onsite and offsite organizations shall include the positions for activities affecting the safety of _the nuclear power plant.

Lines'of authority, responsibility, and communication shall be a.

established and defined from.the highest management levels through intermediate levels to and including all operating organization-positions.

These relationships shall be documented and updated, as o

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appropriate-in the form of organization charts, functional descrip-E L

tions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be docimented in the L

FSAR.

b.

The senior Vice president - Nuclear Operations shall have corporate responsibility for overall plant nuclear safety and'shall take any seasures needed to ensure. acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

The Plant Manager shall be responsible for overall unit safe opera-c.

tion and shall have control over those onsite activities necessary-for safe operation and maintenance of the plant.

d.

The individuals 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 orgar.izational freedom to ensure their independence from operating pressures.

6.2.2 UNIT STAFF Each on-duty shift shall.be composed of at least the etnisus shift a.

crew composition shown in Table 6.2-1; L

WATERFORD - UNIT 3 6-1 Amendment No. 18,41

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, ADMINISTRATIVE CONTROLS-UNIT STAFF (Continued)-

b; At least one licensed Operator shall be in the control room when fuel'is in the reactor.

In addition, while the reactor is in MODE 1,.2, 3, or 4. at least one licensed Senior Operator shall be in the control room, c.:

A Health Physics Technician

• shall be on site when fuel is in the

reactor; d.

All CORE ALTERATIONS shall be observed and directly supervised by..

either a licensed Senior _ Reactor Operator or Senior Reactor Operstor Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

Administrative procedures shall be developed and implemented to e.

limit the working hours of individuals of the nuclear power plant operating staff who are responsible for manipulating plant controls.

or for adjusting on-line systems and equipment affecting plant safety which would have an-immediate impact an public health and safety.

Adequate shift coverage shall be maintained without routine heavy

'use of overtime.. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating.

~However,-in the event that: unforeseen problems require substantial amounts of overtime to be used, the following guidelines shall.be followed:

1.

An individual shall not be permitted tr work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift. turnover-time.

2.

~ An individual shall 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, not 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' hours-in;any 7-day period, all exclud-ing 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 /> shall be allowed between work periods, including shift turnover time.

• ThisJrequirement tolerates Health Physics Technician unexpected absences for not more than'2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, provided management takes immediate action to fill the

. required Health Physics Technician position.

I WATERFORD - UNIT 3 6-2 Amendment No. X8, #1, 50, 61 i

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FIGURE 3,4-3 REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (COOLDOWN)

WATERFORD - UNIT 3 3/4 4 31

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REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM ~ WITHDRAWAL SCHEDULE A_

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CAPSULE VESSEL c NUlWER LOCATION.

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'* Withdrawal time may be modified to. coincide with.those refueling outages or plant shutdowns most closely approaching the withdrawal-schedule.

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ADMINISTRATIVE CONTROLS AUDITS (Continued)

The performance of activities required by the Quality Assurance p.

Program to meet the provisions of Regulatory Guide 1.21 Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 197,5 at least once per 12 months.

AUTHORITY 6.5.2.9 The SRC shall report to and advise the Senior Vice President-Nuclear Operations on those areas of responsibility specified in Specifications 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of SRC activities shall be prepared, approved, a0d distributed as indicated below:

Minutes of each SRC meeting hall be prepared, approved, and a.

fo marded to the Senior Vice iresident-Nuclear Operations within 14 days following each meeting, b.

Reports of reviews encompassed by Specification 6.5.2.7 shall oe prepared, approved, and femarded to the Senior Vice President-Nuclear Operations within 14 days following completion of the review.

Audit reports encompassed by Specification 6.5.2.8 shall be. forwarded c.

to the Senior 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 a.

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

Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the SRC and the Vice President-Nuclear.

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

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WATERFORD UNIT 3 6-13 AMENDMENT NO. 18

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ADMINISTRATIVE CONTROLS

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1

.r SAFETY LIMIT VIOLATION (Continued) i a.; lThe NRC Operations Center shall be notified by telephone as soon as 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 Senior Vice President-Nuclear Operations and the SRC 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 i

be reviewed by the PORC. This report shall describe (1) applicable

. I circumstances preceding the violation, (2) effects of the violation upon facility components,. systems, or structures, and (3) corrective.

e action taken to prevent recurrence..

The. Safety. Limit Violation Report shall be submitted to the Commission, c.

the SRC and the Senior Vice President-Nuclear Operations within 14 days

.E of the violation, d..

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

'l 6.8 PROCEDURES AND PROGRAMS 6.8;l Written procedures shall be established, implemented and maintained covering the activities. referenced below; The applicable procedures recommended in Appendix A of Regulatory a.

Guide 1.33, Revision 2, February 1978 and those required for imple-menting the requirements of NUREG-0737.

x b.

' Refueling operations, Surveillance and test activities of safety-related equipment.

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- d.

. Security Plan implementation.

e.

- Emergency Plan-implementation.

Fire Protection Program implementation.

f.

g.-

Modification of Core Protection Calculator (CPC) Addressable Constants, including independent verification of modified' constants.

NOTES:

.(1) Modification to the CPC addressable constants based on information obtained -

-through the Plant Computer - CPC data link shall not be made without_ prior approval of the PORC.

~(2) Modifications to t'he CPC software (including algorithm changes and changes in fuel cycle specific data) shall be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Procedure," that has been determined to be cpplicable to the facility.

c Additions or deletions to CPC Addressable Constants or changes to 1

Addressable Constant software limits values shall not be implemented 4

i without' prior NRC' approval.

h.-

Administrative procedurec implementing the overtime guidelines of Specification 6.2.2e., including provisions for documentation of l

deviations.

1.

PROCESS CONTROL PROGRAM implementation.

[WATERFORD-UNIT 3_

6-14 Amendment No. - 5, 61 a

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