ML20149E066

Rev 2 to Proposed Tech Specs from 870814 Application for Amend to License DPR-22,changing Plant Organization & Requirements for Senior Reactor Operator Requirements for Mgt & Support Staff

ML20149E066
Person / Time
Site:	Prairie Island
Issue date:	01/04/1988
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20149E016	List: ML20149E011 ML20149E035 ML20149E066
References
NUDOCS 8801130211
Download: ML20149E066 (7)

Text

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EXHIBIT B Revision No. 2 to License Amendment Request Dated August 14, 1987 Docket No. 50-263 License No. DPR-22 Exhibit B consists of marked up pages of the Prairie Island Technical Specifications showing the proposed changes as listed below:

Page TS.6.1-2 Figure TS.6.1-2 IS.6.5 4 8801130211 000104 A

DR ADOCK 0" jPy2

TS.6.1-2 REV  ;

D. Each member of the plant staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positicas, except for -(1) the Superintendent Radiation Protection who shall or exceed the qualifica-tions of Regulatory Guide 1.8, September 1975 (2) the Shif t Technical Advisor who shall have a bachelors degree or lent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and- accidents The training program shall be under the direction of a designated ember of Northern States Power management. 7 E. A training program for the fira brigade shall be maintained under the direction of a designated member of Northern States Power management. This program shall meet the requirements of Section 27 of the NFPA Code - 1976 with the exception of training scheduling. Fire brigade training shall be scheduled as set forth in the training program.

F. Administrative procedures shall be developed and i=plemented to limit the working hours of unit staff who perform safety-related functions; e.g.,  !

senior reactor operators, reactor operators, health physicists, auxiliary l operators, and kay maintenance personnel. Procedures shall include the a

.: following provisions:

E5 .

,o, - 1. Adequate shif t covera;e shall be maintained without routine heavy use gI of overtime. The objective shall be to have operating personnel work g ~. a normal 8-hour day. 40-hour week while the plant is operating. F.ow-geg ever, in the event that unforeseen problems require substantial amounts y

2 of overtime to be used , or during extended periods of shutdown for ggg refueling, major maintenance or major plant modifications, on a gz,u temporary basis, the following guidelines shall be followed:

, $o5 a. 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 /> j j3,@ s traight , excluding shif t turnover time.

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U$E7 b. Overtime shoul.d be 11=1ted for all nuclear plant staff personnel

, Y00~ so that total work ti=e does not exceed 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour

8. E o '# 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 peri.cd , nor more than 5 "?Es 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> in any seven day period , all excluding shif t turnover time. l

- 8 as Individuals should nat be required to work more than 15 consecutive 1 2,5 Z s days without two consecutive days off. ,

E"u3 A break of at least eight hours including shif t turnover time

$ g s "* c.

a y o ,c  : should be allowed between work period s.

5 .E :s l m ';; w3 d. Except during extended shutdown periods, the use of overtime should I

C -g g,g be considered on an individual basis and not for the entire staff eogg n a shift.

E 5 5 E' Shif t Technical Advisor (STA) and Shif t Emergency Coordinator (SEC) on-site rest time periods shall not be considered as hours worked when determining the total work time for which the above limitations apply.

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TS.6.5-4 REV.

E. Offsite Dose Calculation Manual (ODCM)

The CDCM shall be approved by the Co==ission prior to initial i=ple=entation. Changes to the ODCM shall satisfy the following require =ents:

1. Shall be submitted to the Co==1ssion with the Se=1-Annual Radio-active Effluent Report for the peried in which the change (s) were

=ade effective. This-sub=ittal shall contain:

a. sufficiently detailed infor=ation to totally support the rationale for the change without benefit of additional or supple = ental infor=ation. Infor=ation sub=itted should censist of a package of those p1ges of the ODCM to be changed with each page nu=bered and provided with a revision date, together with appropriate analyses or evaluations justifying the change (s).

b. a deter =1 nation that the change vill not reduce the accuracy or reliability of dose calculations or setpoint deter =inations; and .

c. docu=entation of tra fact that the change has been reviewed and found acceptabic by the Operations Cc==ittee. ,

2. Shall becc=e effective upon review and acceptance by the Operations Co=aittee.

F. Security Procedures snall be developed to i=ple=ent the require =ents of the Security Plan and .he Security Contingency Plan. These i=ple=enting ,

procedures, with cne exception of those non-safety related proce- -

dures which govern verk activities exclusively applicable to or perfor ed by security personnel, shall-be' reviewed by the Opera-tions Cc==ittee and approved by a =e=ber of plant manage =ent designated by the Plant Manager. Security procedures not reviewed by the Operations Co==ittee shall be reviewed and approved by the Supervisor, Security and Services. W G. Temporary Changes to Procedures =ay be =ade with the concurrence of two r1=bers of the unit manage =ent Te=porary changes to Operation- Co--' 'aff at Nwleast one of w a +v . p13t="" '"ho= holds a Senior described in A,3,C.D,E and oftheoriginalprocedure:~['5;:bove, which 2de ri? do not change 9.; ;n.n.-.;c;- the License.

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inte. Reactor

• Op indicidu;l;-hc-ldin; ;;ni;; ;;;:st;; 1.;;n;;;. Such changes ahall be 2

docu=ented, reviewed by the Operations Co==ittee and approved by a

=e=ber of plant =anage=ent designated by the Plant Manager within one conth.

Te=perary changes to security procedures not reviewed by i

the Operations Co==1ttee shall ba revieved by two (2) individuals l

knevledt eable in the area affected by the proc-4.ure.

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EXHIBIT C Revision No. 2 to License Amendment Request Dated August 14, 1987 Docket No. 50-263 License No. DPR-22 Exhibit C consists of retyped pages of the Prairie Island Techni-cal Specifications showing the proposed changes as listed below:

Page TS.6.1 2 Figure TS.6.1-2 TS.6.5-4 i

I i

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TS.6.1-2 REV D. Each member of the plant staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positions, except for (1) the Superintendent Radiation Protection who shall meet or exceed the qualifi-cations of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor who shall have a bachelors degree or equivalent in a scientific or engineering discipline with specific training in plant design, and re-sponse and analysis of the plant for transients and accidents, and (3) the General Superintendent Plant Operations who shall meet the requirements of ANSI N18.1-1971, except that NRC license requirements are as specified in FIGURE TS 6.1-2.

E. A training program for the fire brigade shall be maintained under the direction of a designated member of Northern States Power management.

This program shall meet the requirements of Section 27 of the NFPA Code -

1976 with the exception of training scheduling. Fire brigade training shall be scheduled as set forth in the training program.

F. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g. ,

senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel. Procedures shall include the following provisions:

1. 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 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> week while the plant is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:

a. 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 /> straight, excluding shift turnover time.

b. Overtime should be limited for all nuclear plant staff persotinel so that total work time does not exceed 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 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> in any seven day period, all excluding shift turnover time. Individuals should not be required to work more than 15 consecutive days withouc two consecutive days off.

c. A break of at least eight hours including shift turnover time should be allowed between work periods.

d. 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.

e. Shift Technical Advisor (STA) and Shift Emergency Coordinator (SEC) on-site rest time periods shall not be considered as hours worked when ,

determining the total work time for which the above limitations apply.  !

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TS.6.5-4 REV E. Offsite Dose Calculation Manual (ODCM)

The ODCM shall be approved by the Commission prior to initial impicmentation. Changes to the ODCM shall satisfy the following requirements:

1. Shall be submitted to the Commission with the Semi-Annual Radio-active Effluent Report for the period in which the change (s) were made effective. This submittal shall contain:

a. sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with a revision date, together with appropriate analyses or evaluations justifying the change (s),

b. a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and

c. documentation of the fact that the change has been reviewed and found acceptable by the Operations Committee.

2. Shall become effective upon review and acceptance by the Operations Committee.

F. Security Procedures shall be developed to implement the requirements of the Security Plan and the Security Contingency Plan. These implemen-ting procedures, with the exception of those non safety related procedures which govern work activities exclusively applicable to or performed by security personnel, shall be reviewed by the Opera-tions Committee and approved by a member of plant management designated by the Plant manager. Security procedures not reviewed by the Operations Committee shall be reviewed and approved by the Supervisor, Security and Services.  ;

G. Temporary Changes to Procedures i

i Temporary changes to Operations Committee reviewed procedures  !

described in A, B, C, D, E, and F above, which do not change the intent of the original procedure may be made with the concurrence of two members of the unit management staff, at least one of whom holds a Senior Reactor Operator License. Such changes shall be documented, reviewed by the Operations Committee, and approved by a {

member of plant management designated by the Plant Manager within one month.

Temporary changes to security procedures not reviewed by the  !

Operations Committee shall be reviewed by two (2) individuals j knowledgeable in the area affected by the procedure, i l

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