ML20009F444

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Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737 Containment Isolation Setpoint for Rancho Seco Nuclear Power Plant
ML20009F444
Person / Time
Site: Rancho Seco
Issue date: 05/31/1981
From: Broderick N, Ruvalcaba W, Wade W
EG&G, INC.
To:
Shared Package
ML20009F436 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM SRO-270, NUDOCS 8107310159
Download: ML20009F444 (2)


Text

l Energy Measurements Group San Ramon Operatione SRC-270 May 1931 TECHNICAL EVALUATION OF THE RESPONSE TO POSITION NO.5 OF ITEMII. E. 4.2 OF NUREG-0737 CONTAINMENT ISOLATION SETPOINT FOR THE RANCHO SECO NUCLEAR' POWER PLANT (D O CK ET N O. 50 312 )

by W. O. Wade Approved for Puolicat on hA i/ t W. R. duvalCaDa Cesart. ment Manager i

Tnis cocw.ent is UNCLASSIFIED v'

M ier*

M s

~

N1Cnoi W ~.. broGer1CK DepaN. ment Manager Worm Derformeo fer Lawrence Livermore National Lacoratory under U.S. Decartment of Energy Contract No. CE.ACO8 75 NVQ 1183.

8107310159 810714 PDR ADOCK 05000312 P

PDR

INTRODUCTION AND SACKGROUND As a consequence of :ne incident at TMI-2, implementation of a numoer of new requirements nas oeen recommended for operating reac: ors.

Tnese new requirements are described in NOREG-0660, "NRC Action Plan Devel-aced as a Result of tne TMI-2 Accident," Aay 1980, and NUREG-0737, "Clari-fication of IMI Action Plan Requirements," Novemoer 1980.

Tne NRC staff nas also requested licensees to sucmit information sufficient to permit an independent evaluation of tneir response to tnese new requirements.

Ynis report provides an evaluation of tne response to Action Plan Item II.E.4.2, position 5, by tne designated licensee.

CESIGN 3 ASIS CR REVIEW CRITERIA Position 5 requires :na: tne containment pressure sarpoint :nat initiates containment isolation for non-essential system containment vesse!

penetrations te at, or reduced to,

"...tne minimum compatible witn noceal opera:ing ccccitions."

TECHNICAL EVALUATION Response evaluation is cased upon tne values providec for tne following oarameters:

(1)

The maximur c* sseved or e.4;ec;vd containment pressure during nottal opt ration.

(2)

Tne loop error and coserved cri f: in ene pressure sensing instrumentation providing tne isolation signal l

(see note).

(3)

The containment isolation pressure se: point.

NOTE: Tne clarification document (NOREG-0737) provided only

ne expected margin for instrument error and cid not specify acceptacle values for instrument drif: or atmospneric cnanges contricuting to :ne total sensing loop error.

Additional staff guidanca estaclisned a limit of 3.0 psi for an isolation setpoint margin over tne normal containment pressure to account for total loop error.. In addition, foc sueatmosqner,ic contain-ments, a 3.0 psi setpoint margin over' atmosoneric l

pressure is also consicered acceptacle.

l In consideration of :nese values, ne isolation pressure setooint is to se as low as prac:ical witnaut increasing the procaoility of inaover-

ent activation of :ne isolation signal.

CONCLUSIONS The letter of January 16, 1981, suomit:ed oy Sacramento Municipal Utility District, provided sufficient information to concluce :nat :ne containment iscla: ion pressure se:coint for Rancno Seca Nuclear Power Plan meets :ne NUREG-0660/0737 requirements anc is wi:nin :ne accitional limi:-

ing guicelines provided oy :ne NRC s:aff.

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