ML19263F736
| ML19263F736 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, Peach Bottom, Oconee, Palisades, Indian Point, Arkansas Nuclear, Brunswick, Turkey Point, Crystal River, Zion, 05000000, Fort Saint Vrain |
| Issue date: | 01/10/1980 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Ippolito T, Schwencer A, Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19239A281 | List: |
| References | |
| FOIA-81-405 TAC-12365, NUDOCS 8003130391 | |
| Download: ML19263F736 (9) | |
Text
.
I'EPORANDUf1 FOR:
A. Schwencer, DDR T. Ippolitb; DOR D. Ziemann. 00R R. Reid, D0R T. Harpster IE G. Kuzmycz, DPf1 FROM:
Darrell G. Eisenhut, Acting Director Division of Operating Reactors, NRR
SUBJECT:
JANUARY SITE VISITS FOR LESS0!!S LEAR:!ED VERIFICATICN During January the lessons learned inplementation teams will be visiting the plants identified in enclosure 1 to verify icpie.entation of Category A lessons learned requirements. In addition to the ravicw teams, the DCR PM and IE regional principal or resident inspector shculd nrticipate in those reviews.
The DOR pro? ct managers 'should contact the plant and the IE Region to arrange for t.iese visits. outlines the review effort proposed to verify Category A implementation. Those itecs noted for IE revicw should be checked during the site visits. The acceptance criteria for each of these items is contained in Denton's October 30, 1979 clarification letter.
{riginst Signed By:
Darrell G. Eisenhut, Acting Director Division of Operating acactors, !E Enclosurest As stated cc:
W. Gannill I
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R. Vollmer
- 5. Bryan, IE D
Team Leaders
<d' R. Tedesco f/
J. Voglewede O. Vassallo DISTRIBUTIO!!:
9' Central Files HRDenton (U
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00R Reading EGCase JTelford CNelson 3
DEisenhut 8003130 1
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NRC FORM 318 (9-76) NRCM C240 D U.S. GOV E Rfe ENT PRINTING OF Ff CE: 1979 289 369
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NUCLEAR REGULATORY COMMISSION 3 y\\
/ E WASHINGTON, D. C. 20555 J4;UMY :
MEMORAtIDUM FOR:
A. Schwencer, D0R T. Ippolito, DOR D. Ziemann, DOR l
R. Reid, 00R l
T. Harpster, IE G. Kuzmycz, DPM FROM:
Darrell G. Eisenhut, Acting Director Division of Operating Reactors, NRR
SUBJECT:
JANUARY SITE VISITS FOR LESSONS LEARNED VERIFICATION During January the lessons learned implementation teams will be visiting the plants identified in enclosure 1 to verify implementation of Category A lessons learned reauirements.
In additior. to the review teams, the DOR PM and IE regional principal or resident ins:ector should participate i, these reviews.
The 00R project managers should contact the plant and the IE Region to arrange for these visits. o nlines the review effort proposed to verify Category A inclementation. Those items noted for IE rev'.w should be checked during the site visits. The acceptance criteria for each of these items is contained in Denton's October 30, 1979 larification letter.
x
%$llMU %lu Darrell G. Eisenhut, Acting Director Division of 0:erating Reactors, NRR
Enclosures:
As stated cc:
W. Gammill R. Voliner S. Bryan, IE Team Leaders R. Tedesco J. Voglewede D. Vassallo
JANUARY 1980 LESSONS LEARNED SITE VISITS
- January Date GE PLANTS Brunswick 1/2 14/15 Hatch 1/2 16/17 Peach Bottom 2/3 22/23 CE PLANTS Millstone 14/15 Palisades 17/18 Ft. St. Vrain 21/22 Westinchouse PLANTS Turkey Point 3/4 17.18 Zion 1/2 21/22 Indian Point 2/3 23/24/25 B&W PLANTS Oconee 1/2 - 3 14/15 Crystal River 17/18 ANO 1/2 21/22
- Plant Selection based on documented completeness.
LESSONS LEARNED CATEGORY A ITEMS IMPLEMENTATION REVIEW 2.1.1 - Emercency Power Supplies NRR 1.
Evaluate analysis of heater (htr.) capacity required for natural circulation (include time to energize) 2.
Evaluate electrical design:
- diesel capabilities, shedding of htrs, or other loads from buses
- htr. control circuits and power transfer mechanisms
- interface between htrs. & sources
- level inst, PORV's & block valves have vital power supplies, crossconnected as necessary
- emergency power to air supply for ERVs (EWR's) 1.
Review procedures for when and how heater, PORV, block valve and pressurizer level power supplies will be transferi d to vital bus (heed to know time to effect transfer) 2.
Witness power transfer tests 2.1.2 - Relief and Safety Valve Testing NRR 1.
Verify commitment to EPRI or GE BUR Owners Group program or 2.
Verify licensees proposed program and schedule have been submitted
- - Denotes items which will require detailed review prior to NRC approval.
2.1.3a - Direct Indication of Valve Position NRR 1.
Evaluate equipment design (type), method of installation, display, and equipment qualification E
1.
Review procedures for decreasing pressure, LOCA and relief valve actuation for direction to check valve position indi-cators and backup measures 2.
F eck environmental & seismic qualification data 3.
Verify installation and testing of circuits 2.1.3b - Instrumentation for Inadeouate Core Coolino NRR 1.
Evaluate subcooling meter design (e.g., power supplies, corre:t inputs), methods of installation, display, and equipment qualification 2.
Note design of new instrumentation submitted 1.E_
l.
Insure procedures in place for evaluating degree of subcoclir.;
using existing instrumentation, including subcooling meter 2.
Site the subcooling meters and verify continuous display 2.1.4 - Containment Isolation NRR 1.
Evaluate isolation inputs to assure diversity 2.
Note essential and non-essential systems 3.
Evaluate control system to verify-no auto reopening upon rese,
- individual (by valve or penetration) reopening required, and modification does not allow a failure to defeat reset capability
.I E, 1.
Any mods inside containment - check environmental qualificati:n 2.
Review and procedure changes resulting from modifications 2.1.5a - Dedicated Hy Control Penetrations NRR 1,
For licensees whose licensing basis includes require ents for external recombiners or purge systems verify submittal of dedicated co-tain-ment isolation system design and schedule 2.
For all other licensees verify licensing basis does not include such requirements 2.1.Sc - Hydrogen Recombiner Procedures NRR 1.
Determine to which licensees this requirement applies
.L.
1.
Review procedures to assure upgrading for consideration of shielding and personnel exposure at applicable plants 2.1.6a - Systems Intecrity for Hich Radioactivity NRR 1.
Review initial leakage rates and determine impact, if any, en offsite dose analyses 2.
Verify all applicable systens have been tested 3.
Note leak reduction measures taken 4.
Note preventative maintenance program established with leakage rates checked at least once per cycle 5.
Note North Anna type leakage paths addressed
.L.
1.
Verify workable PM program in place covering applicable systems (systems tested initially) with leakage tested at least once per cycle.
2.
Review leakage rate tests 3.
Review leak reduction reasures taken 2.1.6b - Plant Shieldino Review NRR 1.
Verify design review submitted 2.1. 7b - AFW Flow NRR 1.
Review control grade design
.L.
1.
Verify equipment installation and testing
E i..
i 2.1.8a - Post Accident Samoling i
NRR f
1.
Verify design review and description of modifications completed and submitted
(
/
2.
Verify each plant has some sampling capability E
1.
Check that revised procedures for sampling and analysis using as-built system are in effect and provide "best possible" sampling.
Assure that the occupational exposure aspect has been considered in preparing the procedures 2.
Verify any minor modifici ins necessary are complete 3.
Verify training of personnel 2.1.8b - High Range Radiation Monitors E
1.
Assure procedures are in effect and equipment is operational for estimating noble gases and Iodines at high levels (
)
i 2.
Assure procedures include action setpoint whereb, the interim procedures will be activated (keyed to loss of indication on existing equipment) 3.
Verify all potential release paths included 4.
Evaluate to assure protection from background radiation (or other sources) is provided 5.
Assure easy access to readings 6.
Assure comunication with control room 7.
Further details 10/30/79 Denton letter 8.
Verify training of personnel 2.1.8c - Imoroved Iodine Instrumentation E
1.
Verify licensee has provided necessary equipment, training and procedures to determine airborne iodine concentrations in occupied (during post accident situations) areas, includina methods to discriminate background and noble gas interference.
2.
Equipment should be portable (at least some) 3.
A short (10 minutes) turn around time should be assured to provide protection from breathing airborne iodine and relief from unnecessary use of respirators NRR RCS Vent NRR 1.
Verify design submitted 2.2.la - Shift Supervisor Responsibilities E
1.
Review procedures, administri..ive actions, training plans and other licensee actions for compliance with 10/30/79 letter 2.2.lb - Shift Technical Advisor (STA)
NRR 1.
Review STA position for compliance with 10/30/79 letter E
1.
Verify STA position filled and designated on watchbill 2.
Verify STA available within 10 minutes of being summoned 3.
Review procedures for summoning STA to give confidence that he will be utilized 2.2.lc - Shift and Relief Turnover Procedures E
1.
Review procedures for compliance with 10/30/79 Denton letter 2.2.2a - Control Room Access E
1.
Review administrative procedures developed for compliance with 10/30/79 Denton letter
I e, '
2.2.2b - Onsite Technical Support Center (OTSC)
NRR 1.
Note documentation of establishment of OTSC 2.
Note revision to emergency plan IE 1.
Review OTSC to criteria of item 1(A-g) of 10/30/79 Denton letter 2.2.2c - Onsite Operational Suoport Center NRR 1.
Note revision to emergency plan li 1.
Review to criteria of 10/30/79 Denton letter