ML19310A511
| ML19310A511 | |
| Person / Time | |
|---|---|
| Issue date: | 07/16/1979 |
| From: | Capra R NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| To: | Novak T, Ross D NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| Shared Package | |
| ML19310A509 | List: |
| References | |
| NUDOCS 8006170843 | |
| Download: ML19310A511 (3) | |
Text
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UNITED STATES
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2 E WASHINGTo N, D. C. 20555 gv f 16 July 1979 XEMORANDUM FOR:
.D.F. Ross, Jr., Director, Bulletins C Orders Task Force T.H. Novak, Deputy Director, Bulletins & Orders Task Force FROM:
R.A. Capra, BCW Pro ect Manager, Bulletins C Orders Task Force s
SUBJECT:
TMI-2 RELATED ACTION ITEMS FOR B&W PLANTS As you are aware, the B&W Owners Group has formed a Subcommittee for TMI-2 related matters. A meeting is scheduled with the Owners Group on Thursday, July 19, 1979.
In. telephone conversations with Jim Taylor (BSW) and the Subcommittee Chairman Dave Holt (Duke Power Co.), I agreed to provide the Owners Group with a list of agenda items for discussion at the teeting. In coming up with thic list, I have taken items from the following sources: (1) long-term items of the Orders, (2) long-term items resulting from our Safety Evaluations of the Licensees' compliance with these Orders and (3) recommendations of the Leassons Learned Task Force (items which BCO may implement).
LONG-TERM ACTION ITEMS RE0UIRED BY ORDERS:
1.
Failure Mode and Effects Analysis for the ICS 2.
Upgrade of LOMFW and/or Turbine Trip Reactor Trip to safety-grade 3.
Continued operator training and drilling to assure a high state of preparedness SER-LONG' TERM ACTION ITEMS:
1.
Analyses: LOFW and other anticipated transients 2.
Analyses: small break LOCA 3.
Analyses: lift frequency and mechanical reliability of pressurizer PORV and safety valves 4.
Pressure vessel integrity: P-T curve and BCW thermal-mechanical report 5.
AFW/EFW reliability study LESSONS LEARNED RECOMMENDATIONS 1.
. Emergency power for PZR heaters, PohV (and block valve) and PZR level indication 2.
Performance testing for PZR relief valves 3.
Direct indication for PORV 4.
Instrumentation for inadequate. core cooling 5.
Containment isolation diversity 6.
AFW - Auto-initiate (covered by Orders) 7.
AFW - flow indiaction (covered by Orders) 8.
Analyses (any other analyses not covered under Orders or SEs) 9.
Shift supervisor responsibilities 10 Shi ft ' turnover
- 11. Control room access control In addition to this list of generic items, I have attached a list of plant specific
-items.reaulting from the Orders and safety Evaluations.
30.06170 D
~
o I am sendirg a copy of this memo to BCW and the Owners Group for their consideration in making up agenda items for discussion at Thursday's meeting.
gg_ta.C+ -
Robert A. Capra, BCh Project >!anager Bulletins C Orders Task Force Office of Nuclear Reactor Regulation
Enclosure:
As stated cc:
BCW Owners Group G. Sla:ctis J. Taylor (BCW)
P. Statthews J. Heltemes Z. Rosztoczy S. Israel R. Reid
.o LONG TERM ACTIONS OF ORDERS 0
ANO-1 RS DB-1 CR-3
X X
X X
- 2. SAFETY GRADE RX. TRIP: LOMFW AND/OR T.T.
Xe X
X 1 X
X,
- 3. CONTINUED OPERATOR TRAINING AND DRILLING Xj X
X l X
Xl
- 4. AFW/EFW SYSTEM UPGRADE X
X 1
- 5. INSTALL MOTOR ORIVEN EFW PUMPS X
1
- 6. CONTINUE AFW REVIEW: RELIABILITY AND PERF.
X
- 7. CONTINUED ATTEN. TRANS. ANAL, & S.B. PROC.'
X
- 8. EFW FLOW VERIFICATION IN CONTROL ROOM i
i X
SER LONG TERM ACTIONS
- 1. ANALYSES: LOFW & OTHER ANTIC. TRANS Xl X
,X l
X X
- 2. ANALYSES: SMALL BREAK LOCA X
X X i X
X 3.' ANALYSES: LIFT FRE0. & MECH. REl. PORV & SV X
X X i X
X
A X i X
X
- 5. EFW PUMP OPERABILITY X
t
- 6. THERMOCOUPLE HOOK-UP/ INSTALLATION X
i X
- 7. MOTOR-0PER. EFW POWERED FROM VITAL BUS X
1
- 8. AFW RELIABILITY STUDY A
A X
A
I X
- 10. PERM AUTO. DUAL LEVEL SET POINT FOR S/G 1
i X i SER TESTS OR PROCEDURE REOUIREMENTS
- 1. S/O EFW TESTS: FLOW RATES & FLOW STABILITY X
- 2. VERIFY NOISE LEVEL OK FOR C.R. COMMUNICATION X
- 3. LOW POWER TESTS:
(A) CONTROL EFW/AFW INDEP. OF ICS X
X X
(B) VERIFY MIN. REQUIRED EFW FLOW X
X (C) EFW FLOW RATE INDICATOR X
- 4. AFW FLOW RATE INDICATOR & DYNAMIC BK. TEST X
- 5. AFM PRESSURE SWITCH FOLLOW-UP X
i
- 6. AFW DISCH. VALVE FAILURE FOLLOW-UP X
NOTE A - PRESSURE VESSEL INTEGRITY AND AFW RELIABILITY ISSUES APPLY TO ALL PLANTS EVEN THOUGM NOT SPECIFIED IN ORDERS OR SEs.
NRC ACTION ITEMS:
1.
STAFF EVALUATION OF B&W GENERIC SMALL BREAK ANALYSES 2.
DEVELOP ADDITIONAL & MORE DETAILED GUIDANCE FOR LOFW & OTHER ANTICIFATED TRANS.
3.
DEVELOP MORE DETAILED GUIDANCE FOR SMALL BREAK LOCA ANALYSES 4.
PROVIDE DETAILS ON ANALYSES & APPLICABILITY TO OTHER PWR & BWR (SIMILAR TO NR 0560) 5.
DEVELOP MORE DETAILED GUIDANCE ON PORV & SV DESIGN REQUIREMENTS j
6.
REVIEW OPERATOR TRAINING AS PART OF FACILITIE'S REQUAL, PROGRAM 7.
DEVELOP POSITION ON PRESSURE VESSEL INTERGITY ISSUE S.
IE FOLLOW-UP ON CB-1 PRESSURE SWITCH & DISCHARGE VALVE FAILURES B&W ACTICN ITEMS:
1.
JETAILED THERMAL-MECHANICAL REPORT ON BEHAVIOR OF VESSEL MATERIALS FOR DV INTEG ISSUE