ML20090B377
| ML20090B377 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/11/1982 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Bernero R, Starostecki R, Vollmer R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III), Office of Nuclear Reactor Regulation, NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML082380335 | List:
|
| References | |
| FOIA-91-106 NUDOCS 8202260144 | |
| Download: ML20090B377 (8) | |
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FEB 1 1 1982 MDODANDUM FOR:
Fotert M. Bernero, Director Division of Risk Analysis Richard W. Starostecki, Director Division of Project and Resident Program.
Richard H. Vollmer, Director Division of Engineering (Roger J. Mattsori, Director
/-
D i v'i s i oIIlif' 3y's t em s I n t e g ra t i o n Stephen H. Manauer, Director Division of Safety Technology Hugh L. Thompson, Jr., Acting Director y
Division of Human factors Safety FROM:
Gus.C. Lainas, Assistant Director for Safety Assessment, DL
SUBJECT:
RESPONSE TO REPRESENTATIVE MORRIS UDALL'S LETTER OF FEBRUARY 5,1982 Enclos.ed is a copy of Representative Udall's letter sent to Chairman Palladino regarding various aspects of Ginna's steam generator tube rupture.
It has been marked to deliniate primary areas which you are requested to respond to.
Please 90 ply your responses to me by February 17, 1982.
T. A. Ippolin Chief ORAB, is coordinating this response.
Gus C.
ainas, Assistant Director for Safety Assessm'ent Division of Licensing
Enclosure:
Letter dated 2/5/82 f
O cc w/ enclosure:
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February 5,19 82
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The Bonorable Nunzio Palladino Chairman United States Nuclear Regulatory Commission 6,
Washington, D.C.
20555 7
Dear Mr. Chairman:
As a follow-on to the February 4 briefing, I would i
appreciate the Connission's answers to the following
(
questions in addition to the information requested by Mr. Markey.
(45bfW What is the primary significance of the Ginna incident? (RePot/
NRE[RE:I 1.
What was the leak rate through the break as a function 2.
p p_
(A
( lf b AV
' of time?
What triggered the steam generator tube rupture?
hw 4
NRPjfE:I; 3.
4.' Bad there been indications of leaking steam generator gg, tubes prior to the rupture on January 25?
What was the cause of the PORV's apparent failure to closej D,oes the apparent failure of the PORV to close cause 5.
about the adequacy of the industry's program to test N#1 ocuot bE such valves?
45 bAl What would the course of the incident have been had th fully Racit.1 NRR/2gg PORV block valva failed to close partially orfollowing fa 6.
Did the procedure tor responding to a steam generatur k
in tube rupture contain instructions for act. ions to be ta en 7.
response to
- development of a steam bubble in the reactor
-g:7 pressure vessel?
Was there a need during the incident to take actions not specified in the plant's written operating and emergencyWe 8.
discussed in the RE I procedures?
econsistent with Westinghouse guidelines asJanuary 28 me Had a' water level measuring device been available, wouldYI tye size of..,,
' it have assisted the operators in determinin Urs '. e"th""'
REP 4 9.
the pressu u vessel and 8
the st'eam L.hbble
- o bringing the planv. to a stable conditi g g q
h e m e -y n g y ~ ~
q
n
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ar if a leuk had Ceve3cped in in generally e,
- s "i s
-Im generators,
> c;;rators would have been able to
-,', c
, i '.. : e the " feed and :::ed" process described 1.4 Mr.
- 21s ' January 28 mn.orandum.
~
12.
How*many steam generator tube ruptures per year of the D S'I Ginna magnitude or greater do you expect?
13.
What is the likelihood of several steam tube ruptures occurring at one time?
What is the maximum number of
= simultaneous or near simultaneous steam generator tube bST~
' ruptures that are considered design basis acciJents following which the a can be brought to a safe shutdown condition by following plant operating and emergency procedures?
.14.
Did WASH 1400 or more recent risk assessments determine the probability of occurrence of events in which.one or more RE.s steam senerat,r tube failure's are followed by various combinations of PORV, block valve, and safety value failures?
9 15.
How long did it take to reach cold shutdown?
Is this a
-period longer than desireable?
What was the reason for the
?JELJ.
period being longer than normal?
What kinds of malfunctions during the extended cooldown period might have led to a
'significant release of radioactivity to the environment?
16.
Did any part of the reactor pressure vessel cool at a 45 bA)-
' RE: JT rate in excess of that stipulated in the plant technical gg7eg-specifications?
17.
Was there a capability at Ginna to remotely vent the Edi 37 ireactor pressure vessel hich points?/ Does the Commission
~believe that conditions might develop in PWRs calling for bsI the use of remotely controlled valves for the purose of venting steam?
-18.
At any point during the Ginna event, did the steam generator containing the ruptured tube control the primary RE' 1
. system pressure?/ Are operators at Ginna and other PWRs itrained with respect to actions to be taken when a steam gg p3 l generator controls primary system pressure?
I Sincerely, I
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no
's Chairman 1
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