ML20043H196

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Discusses ACRS 362nd Meeting on 900607-09 Re Generic Issue 84 on C-E Plants W/O PORVs
ML20043H196
Person / Time
Issue date: 06/12/1990
From: Michelson C
Advisory Committee on Reactor Safeguards
To: Carr K
NRC COMMISSION (OCM)
References
REF-GTECI-084, REF-GTECI-NI, TASK-084, TASK-84, TASK-OR ACRS-R-1396, NUDOCS 9006220172
Download: ML20043H196 (2)


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UNITED STATER ACRSR-1396 NUCLEAR REGULATORY COMMISSION c.

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E ADVISORY COMMITTEE ON RFACTOR SAFEGUARDS -

PDR-t WASHINGTON, P. C,30686 June 12, 1990 i

The. Honorable Kenneth M. Carr-Chairman U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Chairman Carr:

SUBJECT:

GENERIC ISSUE-84, COMBUSTION ENGINEERING PLANTS WITHOUT POWER OPERATED RELIEF VALVES-During the 362nd. meeting ' of the Advisory Committee on Reactor Safeguards, -June 9,

.1990, we reviewed the - staff's proposed resolution of Generic Issue-84, "CE Plants'Without^PORVs."

We had the benefit of discussions with = members of - the NRC staff <and -

representatives of Combustion Engineering Incorporated (CE). -We also had the benefit of'the referenced. document.'

Generic Issue-84 (GI-84) applies to six operating CE units that do.

3 not have PORVs or other means to rapidly reduce reactor coolant pressure through the venting ^of steam from the system pressurizer.

These are the six CE-units designed after 1970:

. San Onofre. Units 2 and 3; Waterford Unit 3; and Palo Verde Units 1, 2, and-3..These units do have enhanced capability to reduce pressure by'means of essentially safety grade auxiliary pressurizer spray systems.

This generic issue was established. to determine' if the capacity for " feed and bleed cooling" afforded by PORVs should be required for these units.

Most pressurized water reactors can ' bleed" through PORVs - and " feed" with high pressure makeup pumps as an emergency means for removing decay heat from the' core.

. hile this W

y cooling mode is believed to be useful in reducing-risk of core overheating in some circumstances, the NRC has not made-feed.and bleed capability a requirement.

In its report dated December 15, 1981, the Committee expressed concern over a lack of means to feed and bleed in these-plants-during its review of the CE System-80 standard plant design.

At the committee's request, studies of the pros and cons of installa-tion of PORVs on the CE plants were conducted by NRC and CE.

These studies indicated ambiguity as to whether there would be a small reduction or a small increase in risk resulting from a backfit addition of PORVs.

In 1983, the Committee agreed with a staff decision to incorporate this issue into the then ongoing effort on OMQ u 1

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The Honorable Kenneth M.-

Carr.

2 June 12, 1990 Unresolved Safety Issue (USI) A-45, " Shutdown Decay Heat Removal Requirements."

However, the ultimate resolution of.USI A-45 in 1988 did not explicitly address the PORV concern, which was therefore carried on as GI-84.

The staff has now proposed that installation of PORVs not be required for the affected plants.

The reasons cited for this decision ~are that such action is not required to meet any of the Commission's regulations, and'that a cost benefit analysis, as called for under provisions of the backfit rule, indicates such system modifications are not justified.

In general, risk analyses, which are an important input.to the assessment of cost and benefits, lack the accuracy needed to make decisions about the very small differences in risk, plus or minus, that could be created'by addition of PORVs to these plants, We also note that the risk analyses that have been conducted for resolution of GI-84 were limited in that they did not include consideration of external events as initiators. Nevertheless, we believe that these analyses have been useful and we concur with the staff recommendations.

Sincerely,

/

2

.s m Carlyle Michelson Chairman

Reference:

Draft Commission Paper, " Evaluation of'the Need for Primary System High Capacity Manual Venting Capability on Combustion Engineering.

(CE) Plants Without PORVs (GI-84)," transmitted by memorandum dated i

April 27, 1990 from Warren Minners, Office of Nuclear Regulatory Research, NRC, to Raymond F.

Fraley, ACRS.

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