ML20039C000
| ML20039C000 | |
| Person / Time | |
|---|---|
| Issue date: | 11/27/1981 |
| From: | Palladino N NRC COMMISSION (OCM) |
| To: | Udall M SENATE |
| Shared Package | |
| ML20039C001 | List: |
| References | |
| NUDOCS 8112280260 | |
| Download: ML20039C000 (2) | |
Text
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UNITED STATES C i
'E NUCLEAR REGULATORY COMMISSION
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November 27, 1981 OFFICE oF THE CHAIRMAN lf dWtnk OECj yo The Honorable Morris K. Udall, Chairman j
Subcomittee on Energy and the Environnent
- %:w m@g "3 Comittee on Interior and Insular Affairs 3,
"mm United States House of Representatives 7
Washington, DC 20515 1:e 5 h"
Dear Mr. Chainnan:
This is in response to your September 29, 1981 letter. As you have noted, some uncertainties remain over the reportability of events where voids form in the reactor coolant system of pressurized water reactors, particu-larly in the hot-legs.
The Comission has two actions now in progress to clarify its reporting requirements.
First, to implement the immediate notification requirements mandated in Section 201 of the Nuclear Regulatory Comission Authorization Act of Fiscal Year 1980 (P.L.96-295) and to clarify the existing require-ments in 10 CER 50.72 (Notification of Significant Events), the Comission is proposing amendments to its rules,10 CFR 50.54 and 50.72 respectively.
Second, the Commission plans to modify and codify its requirements on licensee event reporting into a new section of 10 CFR 50 (Section 50.73).
It is my intention to ensure that the dialogue accompanying these rule-making activities resolves disagreements and provides consistent under-standings regarding reportability requirements among the Comission, its staff and licensees. Comission action on the first of these actions is scheduled for the near future, and review of Section 50.73 is now scheduled for early in 1982.
Void formation in WR reactor coolant systems can be significant and thus, it is being addressed in two ways by the actions noted previously. First, if a void formtion creates an unanticipated plant condition not governed by the plant's operating or emergency procedures, the event will be im-mediately reported by phone. This reporting requirement is in accordance with recently approved revisions to 10 CFR 50.72.
Additionally, the staff is developing new reporting requirements for licensee event reports (LER's).
As an exarple of what is being considered, events leading to saturation of the primry coolant in FWR's may be required to be reported even though the plant is in a condition governed by the plant's procedures. The implement-ing details for these plans will be finalized in the rulemaking process.
8112280260 811127 PDR COMMS NRCC.
CORRESPONDENCE P.D_R
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.)k The Honorable Morris K. Udall i I
In regards to the adequacy of current systems and procedures to protect public sa c',y in the event that voids develop in steam generator hot-legs, particularly at B&W reactors, a number of actions have been initiated.
The TMI Action Plan includes requirements to ensure that plant operators have been trained and have adequate procedures to recognize and respond to void formation in systems designed to remove heat from the reactor core. Staff believes these measures are adequate' for the time being, until ongoing engineering reviews are completed and additional actions, if needed, are determined and inplemented.
If we can be of further assistance, please let me know.
Sincerely,
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.P adino Chairman l
cc: Rep. Manuel Lujan i
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