ML20149G060

Amend 58 to License DPR-45,revising Tech Specs to Show possession-only Status,To Reduce Fire Brigade from Five to Three Members & to Reassign Training Responsibilities for Fire Brigade

ML20149G060
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	01/04/1988
From:	Rubenstein L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20149G046	List: ML20149G043 ML20149G060 ML20149G071 ML20149G095
References
NUDOCS 8801150017
Download: ML20149G060 (10)

Text

b

%4

' [uo mievS o UNITED STATES

!" n NUCLEAR REGULATORY COMMISSION

- W ASHINGTON, D. C. 20555

{ <1

%,+...+/

DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409 LA CROSSE DOILING WATER REACTOR (LACBWR)

AMENDMENT TO PROVISIONAL LICENSE Amendment No. 58 License No. DPR-45

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The applications for amendment filed by Dairyland Power Cooperative (the licensee) dated April 7, 1986, March 24, 1987, and August 18, ,

. 1987 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B. The facility will be maintained in confornity with the applications, the provisions of the 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; ard (ii) that such activities will be conducted in compliance with the Comission's regulativns set forth in 10 CFR Chapter I; 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 E. The issuance of this amerdment is in accurdance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have i been satisfied. l I

I Occd$ljg$ PD '

l

t

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and Paragraph 2.C.(2) of Provisional License No. DPR-45 is hereby amendcd to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 58, are hereby incorporated in the license. The licensee shall maintain the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of issuarce.

FOR THE NUCLEAR REGULATORY COMMISSION ssAp;&%

lester 5'. Rubenstein Director *

. Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

Changes to the Technical Specifications Date of Issuance: January 4, 1988 I

i l

1 I

>e-c -mma ,, .m,,-w waw .- ge m gm -

1 ENCLOSURE TO LICENSE AMENDMENT NO. 58 PROVISIONAL LICENSE NO. DPR-45 DOCKET NO. 50-409 Replace the following pages and figures of the Appendix A Technical Specifications as indicated below. The revised pages and figures are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Pages INSERT Pages 6-1 6 6-5 6-5 6-7 6-7 6-8 6-8 6-11 6-11 Remove Figures Insert Figures I

6.2.1-1 6.2.1-1 6.2.2-1 6.2.2-1 P

l

(

t

~---;-----.- -

. . . . l l

)

. f. A Fire Brigade of at least 3 members shall be maintained on site at all times.*

g. At all times when the reactor is critical, or when its controls are being manipulated with fuel in the reactor, the control Room shall be attended by a minimum of two persons, one of whom shall have a valid Operators License and shall have full responsibility for operation of the facility.

h. The working hours of the Reactor Control Operator. Turbine Generator Control Board Operator, the Duty Shift Supervisor, hkchanical Maintenance and Instrument & Electrical Technicians and Auxiliary Operator, when performing duties which may affect nuclear safety, and Health Physics Technicians, when performing radiation protection duties which may affect the safety of the public, shall be limited.

In the event overtime must be used, the following restrictions shall be followed:

1. The specified personnel 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 /> straight, excluding shift turnover time.

2. The specified personnel 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, more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any *

, 4 -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.

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 following overtime before the next scheduled shift for the specified personnel, if the above limits are exceeded.

In the event overtime must be used in excess of the above restrictions, the Plant Superintendent or his designate, must

, authorize the deviation and the cause must be documented.

6.2.3 Shift Technical Advisor The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.

• Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed two hours in order to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.

This provision does not permit any Fire Brigade position to be unnsnned upon shift change due to an oncoming brigade member being late or absent.

6-1 l PC4-20 i Amendment No. 58

DAIRYIAND POWER COOPERATIVE OFFSITE MANAGMENT l BOARD OF. DIRECTORS l l GENERAL MANAGER _l 1

-m 4

l SECRETARY & l l ADMINISTRATIVE l '

~

l ASSISTAVr l I i l I I ASSISTANI l l ASSISTANT l l ASSISTA!C l l DIRECTOR l l ASSISTAhT l l l GENERAL MANAGER l l G MERAL MANAGER l l GENERAL MANAGER l l EXTERNAL l l GENERAL MANAGER l l l FOR ENGINEERING l l FOR l l & CONTROLLER l RELATIONS l l FOR OPERATIONS l l AND l l ADMINISTRATIVE l 9 l TECHNICAL SERVICES _l 7

s 2

o FIGURE 6.2.1-1

-0FFSITE ORGANIZATION E

t

- , , - - - v -- - -

t . . -

I

. l GENERAL MANAGER:  : SAFETY REVIEW COPNITTEE:

: ASSISTANT GENERAL :

: MANAGER FOR OPERATIONS:

: TECHNICAL SUPPORT:  : LACBWR  :  : OPERATIONS  :

: CONTRACTORS  :  : PLANT SUPERINTENDENT:  : REVIEW COPNITTEE:

I I I l

, : QUALITY ASSURANCE:  : ADMINISTRATIVE:  : HEALTH & SAFETY: :ONSITE-TECHNICAL:

! : SUPERVISOR  :  : ASSISTANT :  : SUPERVISOR :  : SUPPORT  :

I  : ENGINEERS *  :

AND  :

HEALTH PHYSICS:  : TECHNICAL  :

QA/QC  :  : TECHNICIANS :  : SUPPORT  :

,  : TECHNICIANS:  : SECRETARIES :

h 2' SECURITY & SAFETY:

SUPERVISOR  :

):  :

MECHANICAL :

'I l MAINTENANCE:  : OPERATIONS SUPERVISOR:

!  : SUPERVISOR :

i MECHANICAL :

y  : MAINTENANCE: l .

!g  : SHIFT  : :INSTRIMENT &:

!g

SUPERVISORS;**  : ELECTRICAL : Note

• Technical Support

ya

TECHNICIANS: Engineer is designated as responsible for Fire I! 2  : PLANT OPERA 10RS: Protection Program and

.l. . Emergency Planning

'i un " ** A Shift Supervisor is DAIRYLAND POWER COOPERATIVE responsible for training LACBWR FACILITY ORGANIZATION FIGURE 6.2.2-1

ADMINISTRATIVE CONTR0!.S 6.3 UNIT STArr QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualificaticns of ANSI N18.1-1971 for comparable positions and the supplemental requirements apecified in Sections A and C of Enclosure of the March 28, 1980 NRC letter to all licensees, except for the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING G.4.1 A retraining and replacement training program for the unit staff shall be maintained which shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

6.4.2 A training program for the Fire Brigades shall be maintained under the direction of the Technical Support Engineer and shall meet the requirements l of Section 27 of the NFPA Code-1975, except for the frequency of Fire Brigade training sessions, which shall be held at least once per 92 days. .

6.5 REVIEW AND AUDIT 6.5.1 Operations Review Committee (ORC)

Function 6.5.1.1 The Operations Review Committee shall function to advise the Plant Superintendent on all matters related to nuclear safety.

• Composition 6.5.1.2 The Operations Review Committee shall be composed of the:

Chairman: Plant Superintendent Members: Operations Supervisor Mechanical Maintenance Supervisor l Security and Safety Supervisor i Health and Safety Supervisor Staff Engineers Shift Supervisors (only 1 per quorum)

Management (non-union) SR0s Alternates:

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

6-5 Amendment No.58 l

ADMINISTRATIVE CORTROLS AUTIIORITY 6.5.1.7 The Opera'. ions Review Committee shallt

a. Recommend in writing to the Plant Superintendent approval or dis-approval of items considered under 6.5.1.6a through d above.

b. Render determinations in writing with regard to whether or riot each item considered under 6.5.1.6a through e above constitutes an unreviewed safety question.

c. 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 General Manager g and the SRC of disagreement between the ORC and the Plant Superintendent; however, the Plant Superintendent shall have to 6.1.1 responsibility of resolution of such disagreements pursuant above.

RECORDS 6.5.1.8 The Operations Review Committee shall maintain written minutes of *

- each ORC meeting that, at a minimum, document the results of all ORC activities performed under the responsibility and authority provisions of r these Technical Specifications. Copies shall be provided to the General  ;

I

. Manager and the SRC.

6.5.2 SAFETY REVIEW COHHITTEE (SRC)

FUNCTION 6.5.2.1 The SAFETY REVIEW COMMITTEE shall function to provide independent review and audit of designated activities in the areas of:

a. Nuclear power plant operations,

b. Nuclear engineering, C. Chemistry and radiochemistry,

d. Metallurgy,

e. Instrumentation and control,

f. Radiological safety, i

g. Hechanical and electrical engineering, and II . Quality assurance practices.

• l l

I LACBWR 6-7 Amendment N4 58

e ADMINISTRATIVE CONTROLS ,

COMPOSITION 6.5.2.2 The SRC shall be composed of the:

Chairman: Consultant ,

Members: Consultant Plant Superintendent Director External Relations General Manager i ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized an determined by the SRC Chairman to

. provida expert advice to the SRC.

HEETING FREQUPNCY 6.5.2.5 The SRC shall meet at least once per six months.

QUORUM .

6.5.2.6 The minimum quorum of the SRC necessary for the performance of the SRC review and audit functions of these Technical Specifications shall consist of the Chairman, or his designated alternate, and at least 3 SRC members, including alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.

REVIEW 6.5.2.1 The Safety Review Committee shall reviews

a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provisions of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question,

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 30.59, 10 CFR.

6-8 Amendment No. 58 LACBWR

~ - .- . -

ADHitalSTRATTVE COf1 TROT S

' I 6.6 REPORTABLE EVENT ACTION 6.6.1 The foll' wing o actions shall be taken for REPORTABLE EVENTS:

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 ORC and ,

General Manager.  ;

submitted to the SRC and the 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall bs taken in the event a Safety l Limit is violated f

s. The unit shall be placed in at least HOT SHUTDOWN within j tWO hours.

b. The NRC Operations Center shall be notified as soon as ,

possibli and in all cases within one hour. The and the SRC shall be.notifie'd l

General Manager. l within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

A, Saf ety Limit Violation Report shall be prepared. The  !

c. j report shall be reviewed by the ORC This report shall j describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit i

components, systems or structures, and (3) correctlye ~

l

- ' action taken to prevent recurrence.

I

d. The Safety Limit Violation Report shall be submitted to and14thedays of ,the

.. General the Commissioni the SRC within violation.  ;

Manager.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and l maintained covering the activities ref erenced belows The applicable procedures recommended in Appendix "A" of a.

Regulatory Guide 1.33, Revision 2, February 1978.

b. Refueling operations.

c. Surveillanceandtestactivitiesofsafeyyrelated og,uipment.

6-11 Amendment No. 58 l