ML20132C554

Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for DC Cook Nuclear Power Plant Units 1 & 2

ML20132C554
Person / Time
Site:	Cook
Issue date:	05/31/1981
From:	Wade W EG&G, INC.
To:
Shared Package
ML17194A983	List: ML20132C554
References
TASK-2.E.4.2, TASK-TM SRO-243, NUDOCS 8107310024
Download: ML20132C554 (3)

Text

.. . _ ._ . _ _ - . . - . = . - _ - . - - - -- -- -- - -

GsG Enorgy McCourements Crsup SRO-243 San Ramon Operatione May 1981 TECHNICAL EVi JATION OF THE RESPONSE TO POSITION No.5 OF ITEM II. E. 4.2 OF NUREG-0737 CONTAINMENT ISOLATION SETPOINT FOR THE D.C. COOK NUCLEAR POWER PLANT UNITS 1 AND 2 (DOCKET Nos. 50 315 and 50 316) by W, O. Wade Approved for Puolication 1

A.s l' b j _

W. R. Ruvalcana Department Manager This document is UNCLASSIFIED l

$$ fi r' s c- M. <<

~ N1cnolas (, Srocericx Department Manager Work Performed for Lawrence Livermore National Laboratory urcor U.S. Department of Energy ontract No OE. ACOS.76 NVQ iisa' 8107310024 810630 CF SUBJ ID&R-STMI CF

e 0 INTRODUCTION AND BACKGROUND As a consecuence of tne incident at TM1-2, impiementation of a number of new requirements nas been recommended for operating reactors.

These new requirements are described in NUREG-0660, "NRC Action Plan Devel-oped as a Result of the TMI- Accident ," May 1980, and NUREG-0737, "Clari-fication of TM1 Action Plan Requirements," November 1980. Tne NRC staf f nas also requested licensees to submit information sufficient to permit an independent evaiuation of tneir response to tnese new requirements. This report provides an evaluation of the response to Action Plan item !!.E.4.2, position 5, by tne designated licensee.

DESIGN 8 ASIS OR REVIEW CRITERIA Position 5 requires tnat tne containment pressure setpoint tnat initiates containment isolation for non-essential system containment vessel penetrations De at, or reduced to, "...tne minimum compatiole witn normal operating conditions."

TECHNICAL EVALUATION Response evaluation is eased upon tne values provided for tne following parameters:

(1) The maximum observed or expected containment pressure during normal operation.

(2) Tne loop error and oeserved drift in tne pressure sensing instrumentation providing tne isolation signal (see note).

(3) Tne containment isolation pressure satpoint.

NOTE: Tne ciarification document (NUREG-0737) provicec only tne expected margin for instrument error and did not specify acceptable values for instrument drift or atmospneric changes contributing to tne total sensir' loop error. Additional staf f guidance estaolisned a limit of 3.0 psi for an isolation setpoint margin over tne normal containment pressure to account for total loop error. In addition, for subatmospneric contain-ments, a 3.0 psi se point margin over atmosoneric pressure is also considered acceptable.

In consideration of tnese values, tne isolation pressure setpoint is to be as low as practical witnout increasing tne probacility of inadver-tent activation of tne isolation signal.

CONCLUSIONS Tne letter of January 8, 1981, suomitted by Indiana and Micnigan Electric Company, provided sufficient information to concluce nat tne con-tainment isolation pressure setpoint for 0. C. Cook Nuclear Power Plant, Units 1 and 2, meets tne NUREG-0660/0737 requirements and is witnin tne -

additional limiting guidelines proviced oy tne NRC staff.

1 Sa fety Evaluation Report Minimum Containment Pressure Setpoint

(! tem !!.E.4.2(5) of NUREG-0737)

D. C. Cook Nuclear Power Plant, Units 1 and 2 -

Docket Nos: 50-315, 316 1.0 Int ro_ duct ion I As a consequence of the accident at TN!-2, implementation of a number of new 1

requirements has been recomended for operating reartors. These new require-ments are described in NUREG-0660, "NRC Action Plan Developed as a Result of the TMI-2 Accident," May 1980, and NUREG-0737, ' Clarification of TMI Action Plan Requirements," November 1980. The NRC, staff has also requested licen-sees to submit infomation suff1ctent to pemit an independent evaluation of their response to these new requirements. This report provides an evaluation of the response to Action Plan Item !!.E.4.2, position 5, by the designated licensee.

2.0 Evaluation Our consultant, the EG&G Energy Measurements Group (a subcontractor to Lawrence Livemore National Laboratory, which has the TMI Action Plan contract) has reviewed the licensee's submittals and prepared the attached technical evaluation report of the licensee's containment pressure setpoint used to isolate nonessential conteinment penetrations. We have reviewed this evaluation and concur in its basis and findings.

3.0 Concl usions The infomation submitted by the licensee provided suffletent details of the licensee's contaiment isolation pressure for the staff to conclude that the requirements of Item II.E,4.2(5) of NUDEG-0737, with the additional guidelines developed by the staff, have been met.

l .

EGcG Energy Wessutomonts Crsup SRO-247 Son Aamen operations May 1981 i

TECHNICAL EVALUATION OF THE RESPONSE TO POSITION NO.5 l OF ITEM 3I. E. 4.2 OF NUREG-0737 CONTAINMENT ISOLATION SETPOINT FOR THE DRESDEN .

NUCLEAR POWER PLANT UNITS 2 AND 3 (DOCKET Nos. 50 237 and 50 249)

D1 W. O. Wade Approved for Puolication A/ l b-W. R. Ruvalcaca Department Manager This cocument is UNCLASSIFIED ass fier: Mw M

~ NICnoldS K brocerict, Department Manager i

Worm Performed forLawrence Livermore Nationallaceratory uncer U.S. Oooartment of Energy Contract No. DE. ACOS.76 NVQ 1180.

synen,r

I INTRODUCTION AND BACKGROUND ~

As a consequence of the incident at TMI 2, implementation of a l number of new requirements has been recomended for operating reactors. I These new requirements are described in NUREG-0660, "NRC Actica Plan Devel. 1 oped as a Result of the TMI-2 Accident," May 1980, and NUREG-0737, "Clari-fication of TM! Action Plan Requirements," November 1980. Ine NRC staff nas also requested licensees to submit information sufficient to permit an independent evaluation of their response to these new requirements. This report provides an evaluation of tne response to Action Plan item !!.E.4.2, position 5, t,y the designated licensee.

l DESIGN BASIS OR REVIEW CRITERIA Position 5 requires tnat tne containment pressure setpoint tnat initiates containment isolation for non essential system containment vessel penetrations be at, or reduced to, "...tne minimum compattole with normal operating conditions."

1ECHNICAL EVALVATION Response evaluation is based upon the values provided for the following-parameters:

t (1) The maximum observed or expected containment pressure during normal operation.

(2) The loop error and observed drift in tne pressure sensing instrumentation providing One isolation signal (seenote). .

(3) The containment isolation pressure setpoint.

' NOTE: The clarification document (NUREG-0737) provided only the expected margin for _ instrumtnt error and did not specify acceptable values for _ instrument drift or-atmospneric changes contributing to tne total sensing loop error. Additional staff guidance establisned a limit of 3.0 psi for an isolation setpoint margin over tne normal containment pressure to account for total loop error. In addition, for subatmospneric contain-ments, a 3.0 psi setpoint margin over atmosoneric pressure is also considered acceptable.

In consideration of these values, the isolation pressure setpoint is to be as low as practical witnout increasing tne procaoility of inadver-tent activation of the isolation signal.

CONCLUSIONS Tne letter of December 31, 1980, submitted by Comonwealtn Ecison Company, provided suf ficient information to conclude tnat tne contat.iment isolation pressure setpoint for Dresden Nuclear Power Plant, Units 2 and 3, meets the NUREG-0660/0737 requirements and is witnin the aeditional limit-ing guidelines provided by the NRC staff. -

w-mMe w wrw=-*=-ee =ww &m r ve r t + -wn w erm em ur-mewue w s- % d 'w- e n e --e g eye e - r Ctr-9-ev-r*=r st - - - , u-ewy wo -,w w eg, eeg e w =g-s tv ry=r <v r - w wr* F ve-er F w vr m *--V M-

- .- - -.- __ .-.-. . -- --. -. - _ . . - - = - - - - . - - -

l Safety Evaluation Report Minimum Containment Pressure Setpoint

(! tem !!.E.4.2(5) of NUREG-0737)

Dresden Nuclear Power Plant, Unit 3 Docket No: 50-249 1.0 Introduction As a consequence of the accident at TMI-2, implementation of a number of new requirements has been recommended for operating reactors. These new require-ments are described in NUREG-0660, 'NRC Action Plan Developed as a Result of the TMI 2 Accident,' May 1980, and WUREG-0737, " Clarification of TMI Action Plan Requirements,' November 1980. The NRC. staff has also requested licen-sees to submit infomation sufficient to pemit an independent evaluation of their response to these new requirements. This report provides an evaluation of the response to Action Plan Item !!.E.4.2, position 5, by the designated licensee.

2.0 Evaluation Our consultant, the EG&G Energy Measurements Group (a subcontractor to Lawrence Livemore National Laboratory, which has the TMI Action Plan contract) has reviewed the licensee's sutaittals and prepared the attached technical evaluation report of the licensee's containment prassure setpoint used to isolate nonessential containment penetrations. We have reviewed this evaluation and concur in its basis and findings.

3.0 Conclu sions The infomation submitted by the licensee provided sufficient details of the licensee s containment isolation pressure for the staff to conclude that the requirements of Item II.E.4.2(S) of NUREG-0737, with the additional guidelines developed by the staff, have been met.

i

% F --

-"N--8,.a+-rW9T"-tath wMO'e

• v 1@' yC"yw r e ys mwy w- r-r-w y gy9g y& gq.ie,y,gm g ypy g my mseg .g g- ,.gw9 3 9 n .p m,.g.,y g p g w p,,-g.n,p..y -

w.w+4by,,, ,,e,.9 , , 9g99 y ..,__,,,.,4