ML19351A367

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Proposed Tech Spec Table 4.4-5 Re Reactor Vessel Matl Surveillance Program - Withdrawal Schedule
ML19351A367
Person / Time
Site: Waterford Entergy icon.png
Issue date: 10/16/1989
From:
LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML19351A366 List:
References
NUDOCS 8910200124
Download: ML19351A367 (8)
v • d • e


Text

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ATTACIMENT A

, NPF-38-104 1

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o 8910200124 891016 FDR P ADOCK 05000332

' PDC

TABLE 4.4-5 EF i S Ti<u's 1

~

M REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITHDRAWAL SCHEDULE

?R S CAPSULE VESSEL LEAD NUMBER LOCATION FACTOR .

WITHOMedikt TIME (TFPY)*

E 1 83* -

1.50 Standby G

l w 2 97* 1.50 4.0 EFPY 3 104* 1.50 11.0 EFPY 1 -

4 284* 1.50 18.0 EFPY 5 263* 1.50 Standby 6 277* 1.50 Standby i

1 M

  • Withdrawal time may be modified to coincide with those refueiing outages or plant shutdowns most closely approaching the withdrawal schedule.

r , , a e .,-e -= + e -rwe - - ww me,,, ,--+r= ~ - -

wv+.-e --

3s- ---w- .=, -+-- ,- - -m- e = w---w,-=~*-- - - - - - - - --- -< =-e

c Eo S Ti e4 Cr l ADMIN!$1RATIVE CONT 80L5 UNITSTAFF(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,Senter Operator shall be in the j l control room. J

c.  !

A Nealth Phsics Technician

  • shall be on site when fuel is in the I reacter; l
d. All CORE ALTERATION $ shall be observed and directly spervised by 1 L either a licensed Senior Reactor Operator or SentLr Reactor Operator l Lietted to Fuel Handlin i de' ring this operation. g who has no other concurrent responsibilij 1
e. Administrative recedures shall be developed and isplemented to I liett the wrkt hours of individuals of the nuclear power plant  ;

operating staff are responsible for manipulating plant controls  ;

l or for adlusting on-line systems and equipment affecting plant safety ,

, which wou!d have an immediate tapact on public health and safety.  :

i Adequate shift coverage shall be maintained without routine heavy i i use of evertfee. The objective shall be to have operating personnel l l

work a nonssi 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day, 40-hour week while the plant is operating. l However, in the event that unforeseen problems require substantial  !

amounts of everttee to be used, the fo11owing guidelines shall be l followed: i

1. An individual shall rot 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. 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 /> $

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 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />  :

in av 24nor period hour more period,72 than hours in av 7 day period, all exclud-  ;

IngshIftturnoverties.  ;

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.

"The Health Phsics Technician and fire brisado composition may be less than the minimum requirteents for a period of ties not to exceed I hours, in order to acconeodate unexpected absence, provided immediate action is taken to fill the required positions.

L WATERFORD - UNIT 3 6-2 Amendment No. 18, II, 50

i

~ ~

EXISTING  !

l

, ADMINISTRATIVE CONTROLS d i

$AFETY LIMIT VIOLATION (Continued)

a. The NRC Operations Center sh' a ll be notified by telephone as soon as f 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 />. l

b. A Safety Limit Violation Report shall be prepared. The report shall  !

+

be reviewed by the PORC. .This report shall describe (1) appitcable i circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective l action taken to prevent recurrence. l

c. The Safety' Limit Violation keport shall be submitted to the Commission, the SRC and the Senior Vice President-Nuclear Operations within 14 days  ;

, of the violation. .

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

i 6.8 PROCEDURES AND PROGRAMS .

6.8.1 Written pro'cedures shall be established, implemented and maintained covering the activities referenced below:

1 a. The applicable procedures recommended in Appendix A of Regulatory l Guide 1.33, Revision 2, February 1978 and those required for imple-menting the requirements of NUREG-0737. ,j l

b. Refueling operations. '
c. Surveillance and test activities of' safety-related equipment. i
d. Security Plan implementation. l
e. Emergency Plan implementation,
f. Fire Protection Program implementation.
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 cf the PORC.

l (2) Modifications to the 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 applicable to the facility.

Additions or deletions to CPC Addressable Constants or changes to Addressable Constant software limits values shall not be implemented without prior NRC approval.

Administrative procedures implementing the overtime guidelines of h.

Specification 6.2.2f. , including provisions for documentation of deviations. .,

i. PROCESS CONTROL PROGRAM implementation.

WATERFORD - UNIT 3 EXISTING s-14 AsENosENT NO. 5

hMW,M'444MMts#%A(A*.NNl  %/ 7MF NM nW I p g-e e 4

e 5

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ATTACHMENT B NPF-38-104 e

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3

' TABLE 4.4-5 O ~

E M REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITHORAWAL SCHEDULE 4

S CAPSULE VESSEL LEAD NUMEER LOCATION FACTOR .

WITHORAMAL TIME (EFW)*

E

~

1 83* -

1.50 Standby

-4 w 2 97* 1.50 4.0 EFPY

! 3 104' 1.50 11.0 EFPY AOD:

4 4 284* 1.50 18.0 EFPY l

5 4 ) 263* 1.50

/ 5tardby

' /

6 ,/ 277* 1.50 Standby w

k

. .DE LET F-b

  • Withdrawal time may be modified to coincide with those refueling outages or plant sistdowns most closely approaching the withdrawal schedule.

w, w y.w,.m.i.-we.--- -mw .

3 j

, k'(,,3 P C., S E. C5 i

ADMINISTRATIVE CONTROLS

' I t

UNIT STAFF (Continued) l l 1

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 j MODE 1, 2, 3, and 4, at least one licensed Senior operator shall i be in the control roo:n. i

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 1 Operator Limited to Fuel Handling who has no other concurrent l

+

responsibilities during this operation.

1

e. Administrative procedures shall be developed and implemented to i limit the working hours of individuals of the nuclear power plant l operating staff who are responsible for manipulating plant l controls or for adjusting on-line systems and equipment affecting plant safety which would have an immediate impact on public l health and safety.  ;

Adequate shift covetage 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 ,

i

- guidelines shall be followed:  :

1. 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 /> straight, excluding shif t 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, 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 enluding shif t turnover time. 1

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.

~ _ . . . - _ . . . . . _ . _ . ._ ,

~_

  • This requirement 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,

/ j.

ww 40 c . . . .,<. w. M b e . pid (8d'T 9 WATER}T)RD - UNIT 3 6-2 Amendment No. 41

- I PROPOSED l ADMINISTRATIVE CONTROLS i SAFETY LIMIT VIOLATION (Continued) '

a. The 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 />. l
b. A Safety Limit Violation Report shall be prepared. The report shall i I

be reviewed by the PORC. This report shall describe (1) applicable l circumstances preceding the violation, (2) effects of the violation l

upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence. l

- c. The Safety' Limit Violation Report shall be submitted to the Commission, l the SRC and the Senior Vice President-Nuclear Opefations within 14 days of the violation. ,

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

6.8 PROCE00RE3 AND PROGRAMS .

6.8.1 Written pro'cedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978 and those required for imple-menting the requi;ements of NUREG-0737.
b. Refueling operations,
c. Surveillance and test activities of' safety-related equipment.
d. Security Plan implementation.
e. Emergency Plan implementation,
f. Fire Protection Program implementation.
g. Modification of Core Protection Calculator (CPC) Addressable Constants, including independent verification of modified constants.

NOTES:

l (1) Modification to the CPC addressable constants based on infomation obtained through the Plant Computer - CPC data link shall not be made without prior approval of the PORC.

(2) Modifications to the CPC software (including algorithm changes and changes in fuel cycle specific data) shall be performed in accordance with the most L

recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Procedure," that has been determined to be applicable to the facility.

Additions or deletions to CPC Addressable Constants or changes to -

Addressable Constant software limits values shall not be implemented without prior NRC approval.

h. Administrative dures implementing the overtime guidelines of Specification 6.2.2 ,ingludingprovisionsfordocumentationof

( g,h (

, deviations.

De m

1. PROCESS CONTROL PROGRAM implementation.

AMENDMENT NO. 5 WATERFORD-UNIT 3fQQf]${}6-14

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