ML051460155
| ML051460155 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/18/2005 |
| From: | Blough A Division Reactor Projects I |
| To: | Wiggins J NRC Region 1 |
| References | |
| FOIA/PA-2005-0207 | |
| Download: ML051460155 (4) | |
Text
A. Rardolph Blough - Fwd: Millstone Event - Suggested Areas for Followup - -
From:
A. Randolph Blough To:
Wiggins, James Date:
4/18/05 7:59AM
Subject:
Fwd: Millstone Event - Suggested Areas for Followup - -
these notes were developed in IRC to help formulate the followup team insp plan Pagej CC:
Collins, Samuel
IA. Randolph Blough - Millstone Event - Suggested Areas for Followup Page 1 1 From:
To:
Max Schneider; Date:
Subject:
Region 1 Incident Response Center Barry Norris; Blough, A. Randolph; Brian Holian; John Monninger; Kevin Mangan; Paul Krohn; Scott Barber; Silas Kennedy; Wayne Lanning 4/17/05 6:01PM Millstone Event - Suggested Areas for Followup See attached suggested areas for followup for your review and consideration.
! cAtemp\\GW}00001.TMP Page 1 Mlail Envelope Propertics (4263A120.1CD :9: 34932)
Subject:
Fwd: Millstone Event - Suggested Areas for Followup - -
Creation Date:
4/18/05 7:59AM From:
A. Randolph Blough Created By:
ARB(nrc.gov Recipients Action l)ate d nrc.gov kpl_po.KPDO Delivered 04/18/
JTWI (James Wiggins)
Opened 04/18/
Deleted 04/19/
SJCI CC (Samuel Collins)
Opened 04/18/
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'05 01:33PM 05 08:OOAM 05 08:21AM v
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A. Randolph Blough - Millstone 3 Safety Relief Valve Event.wpd,-
Page 1 SUGGESTED AREA FOR FOLLOW-UP Millstone Unit 3 Reactor Trip/Safety Iniection EAL Alert Declared - Main Steam Line Safety Valve Failed to Reseat
- 1)
Understand initiation of event and its cause(s), as well as the detailed event sequence (In particular, any relation to previous maintenance, equipment issues, or precursor events).
- 2)
Understand safety system response, such a why only Train - 'A' SIAS/MSI actuated automatically.
- 3)
Understand equipment performance, including:
Trip of turbine-driven auxiliary feedwater pump.
I.
Charging system valve packing leakage (leaked - 1000 gallons of RCS into the Primary Auxiliary Building).
Behavior of steam generator safeties, PORVs, primary reliefs.
PORVs and primary safeties condition including an assessment of potential damage which could have occurred as a result of water relief.
- 4)
Understand application of the Technical Specifications and Technical Specification action statement time limits (e.g., time required to reach hot shutdown with inoperable steam generator safety valves).
- 5)
Understand licensee operational performance, including:
Operator initial response.
use of EAL's/implementation of EOP's, AOP's E-Plan.
response to plant equipment issues, including:
- continuing input into PRT (should they have investigated sooner and reacted sooner to indication of PORV leakage)
- efforts to confirm that no primary-to-secondary leakage was occurring; including SIG sampling and other evaluations and analyses (also decisionmaking about steaming from the 'D' SIG w/o a sample).
- 6)
Evaluate the licensee post-event assessments, including causal analyses, extent-of-condition reviews, prompt corrective actions before restart, and longer term corrective and preventive measures.