IR 05000333/1990004
| ML20062B833 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/09/1990 |
| From: | Hehl C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Fernandez W POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| EA-90-136, NUDOCS 9010260159 | |
| Download: ML20062B833 (16) | |
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OCT 0 91990, Docket No.
50-333 Lic. No.
DRP-59 EA No.90-136 New York Power Authority James A. FitzPatrick Nuclear Power Plant A1TN:
Resident Manager i
P.O. Box 41 Lycoming, New York 13093
Gentlemen:
Subject:
RESULTS OF THE AUGUST 21,1990 ENFORCEMENT CONFERENCE.
(INSPECTION REPORT 50-333/90-04)
On August 21,1990, you and members of your staff attended an enforcement conference
at the Region I office to discuss the apparent violations identified in Inspection Report 50-333/90-04. Specifically, the apparent violations concerned the potential that the FitzPatrick
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emergency service water (ESW) system would not have _ performed its. designed safety j
function during the operating cycle prior to the 1990 refueling outage and the adequacy of-t your previous actions to identify and correct the deficiencies with the ESW system.
At the enforcement conference you stated that your evaluations have _ determined that although the ESW system was in a degraded condition prior to the 1990 outage, the ESW
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system would have been able to perform its design function. Based on our review of your
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evaluation, we agree with the overall conclusion. Accordingly, we are not issuing a notice of violation regarding the operability of the ESW system in Inspection Report 50-333/90-04.
In addition, we reviewed the apparent violation regarding your corrective actions following the 1989 Severity Level III violation. Specifically, those corrective actions addressed the ~
clogging of safety-related unit coolers, but did not address the potential clogging of the piping and check valves within the ESW system. While a more vigorous approach could
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have addressed this potential problem such that the degraded conditions would have been detected and corrected earlier, we have concluded that your corrective actions were reasonable given the extent of the unit cooler problem. Further, after the degraded j
conditions were. identified during the recent outage, your extensive corrective actions were
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effective in evaluating the system's condition, repairing ' nd replacing degraded components, a
and confirming the design of the system with analysis and. testing prior to ' returning the-i system to service. Accordingly, we are not issuing a notice of violation concerning corrective actions related to the 1989 unit cooler violation.
9010260159 901009
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PDR ADOCK 05000333 O
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OCT 091990
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New York Power Authority
It is important that you continue to review the testing being conducted on safety-related systems and components to ensure that design requirements are being met. In this regard -
we note that you are currently developing a new surveillance program, including guidelines to be used to determine the adequacy of testing. We encourage the development of such
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a program.
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At the enforcement conference, it was apparent that there was a misunderstanding between us regarding your commitments following' the crescent area cooler violation. Specifically, despite the documentation of our understanding of a commitment on testing.to be conducted on other coolers in the ESW system in two inspection reports, you stated that you -
did not have such a commitment and did not recall the discussions documented within the i
inspection reports. In the future we will reference such discussions in the forwarding letters for inspection reports and request that such commitments be formally acknowledged. We ask that you bring any such future misunderstanding regarding commitments to our attention.
A list of enforcement conference attendees is included as Attachment 1 to this letter. Also attached are pertinent portions of the information package used to support your enforcement conference presentation (Attachment 2), including a section which denotes your
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knowledge of the status of known commitments to NRC related to the ESW issue. Due to the previously noted conflicts with regard to the understanding of certain ESW commitments, we request that you respond to this letter and update the status of these known commitments with planned dates of completion for those actions indicated as on-
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going, pending, partially complete or continuing from the previous crescent area cooler issues. Also, please address the status of additionalissues discussed during the enforcement
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conference, namely, the ESW system testing program that is currently being implemented, the submittal of an ESW technical specification change, and the submittal of a revised L
response to NRC Generic Letter 89-13.
l In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice" a copy of this letter will
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be placed in the NRC Public Document Room.
Since
-Charles W. Hehl, Director
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Division of Reactor Projects
Attachments:
As Stated
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OCT 0 91990 New York Power Authority l
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REGION 1 NRC C. IIchl, Director, DRP C. Cowgill, Acting Chief, Projects Branch No.1, DRP G. Meyer, Chief, Reactor Projects Section 18, DRP W. Schmidt, Senior Resident inspector, FitzPatrick R. Plasse, Resident Inspector, FitzPatrick R. Capra, Director, Projects Directorate 1-1, NRR D. LaBarge, NRR Project Manager, FitzPatrick M. Case, Operations Engineer, NRR
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R. Gallo, Chief, Operations Branch, DRS M. Chiramal, Acting Chief, Special Test Programs Section, DRS D. Florek, Senior Operations Engineer, DRS D.1-lolody, Enforcement Officer, Region I W. Troskoski, Office of Enforcement NYPA S. Zulla, Vice President - Nuclear Engineering R. Beedle, Vice President - Nuclear Support W. Fernandez, Resident Manager V. Walz, Technical Services Superintendent D. Wallace, Performance Engineering Supervisor D. Kerr, Performance Engineer C. Ponzi, System Engineer B. Young, Manager, Mechanical Engineering J. Elmers, Acting BWR Licensing Manager D. Wille, Manager, Nuclear Projects Manager (Stone & Webster)
H. Greenberg, Assistant Manager, Nuclear Projects Division (Stone & Webster)
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NEW.. YORK POWER AUTHORITY a
JAMES A.
FITZPATRICK. NUCLEAR POWER? PLANT
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TABLE OF CONTENTS
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L O EaER.ENCv SERVICE WATEa Sv5 tea oESIGN OvERv1EW j
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PRESENTATION SUMARY III. EVOLUTION OF ESW SYSTEM AW CHECK VALVE:
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INSPECTION / TESTING' ISSUES H
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L IV.
SAFETY REVIEW 0F 1990 REFUELING OUTAGE FININGS l
A.
ELECTRIC' BAY-(EAST)'
B.
ELECTRIC BAY (WEST)
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CABLE TUNNEL.(EAST)
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CAsLE' TUNNEL (WEST)
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CONTROL ROOM / RELAY ROOM VENTILATION
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CRESCENT (ECCS EQUIPMENT) AREAS (EAST AND WEST)
o STATUS OF PREVIOUS.1RC COMITNENTS.
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VI.
JAF SERVICE WATER SYSTEM UPGRADE MODIFICATIONS AND IMPROVEMENTS l
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VII. APPENDICES
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A.
NRC INSPECTION-REPORT.50-333/90-04 B.
CHRONOLOGY OF'ESW/SW SYSTEM AND CHECK VALVE ISSUES-.
C.
1990 REFUELING OUTAGE ACTION CHRONOLOGY 1.
SHORT-TERM TASK-LISTING
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D.
ESW/SW CHECK VALVE INSPECTION: RESuLTS (1987-1990)-
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1988 CRESCENT AREA UNIT' COOLER REFERENCE-DOCUMENTS-
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LER-88-09-INOPERABLE ECCS ARsA COOLING DUE-T0. INADEQUATE 4.
-PROCEDURES
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EN,0RCE ENT CON,ERE CE CORRECTIVE ACTION NATRIx (01/13/89)
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3.
NYPA LETTER JAFP 89-0284 (04/12/89) - RESPONSE TO NOTICE.0F
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VIOLATIONi
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EMERGENCY SERVICE WATER i
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Descrintion of system:
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The system consists of two independent supply loops, each
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supplied from one emergency service water-pump'which takes suction from the Pumphouse forebays.
Each loop is designed to.
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supply raw cooling water to one train of the following equipment:
EDG Jacket Cooling Water Heat Exchangers (93WE-1A,B,C,D)
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Electric Bay Unit Coolers (67UC-16A,B)
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Cable Tunnel /Switchgear Room Coolers (67E-11, 14)'
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Control Room Chiller Condensers (70RWC-2A,B)
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Control Room Ventilation Chiller Condenser Room Air Handling
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Units (70AHU-19A,B)
Crescent Area Unit Coolers (66UC-22A through K)
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- RHR Pump Seal Coolers (10E-3A,B,C,D)
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- CRD Pump Oil and Bearing Coolers.(03P-16A,B)
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- Recirc. Pump and Motor Coolers'(02-2P-1A,B)
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- PASS Cooler (SSC-LSC-1)
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- Drywell Area Coolers (68E-1A,B,C,D/68E-3A,B,C,D)
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Normally supplied cooling by Reactor Building Closed
Loop Cooling System.
The ESW System operates automatically on a: loss of Reactor Building Closed Loop Cooling (RBCLC) by low'RBCLC: System pressure or upon start of the Emergency Diesel Generators.
The ESW pumps-and associated injection valves can also be remotely operated from the Control Room.
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The individual trains.cf EDG jacket cooling water heat
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exchangers, Electric. Bay unit coolers,-Cable' Tunnel /Switchgear
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Room coolers, control Room chiller condensers, Control-Room ventilation chiller condenser room AHUs, Crescent Area unit coolers, RHR pump seal coolers, CRD pump coolers, and recirc.
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pump and motor coolers receive ESW supply =when the associated train of ESW pump is-started and the trainninjection valve 46MOV-
101A or B is opened.
The drywell equipment' drain sump cooler, drywell coolers, and Control Room-and Relay Room air handling O
units require operator action to initiate ESW supply.
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EMERGENCY SERVICE WATER
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Additional flexibility of the system has been provided through
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the capability of cross-tying the A and.B train supply of ESW to the Reactor Building ESWoloads.
This option is only for
flexibility and is not a design requirement.
ALsummary of the r
Emergency Service Water System safety-related' heat loads and required raw water flow rates as defined in JAF. Safety Evaluation
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JAF-SE-90-067, Clarification of the Design Basis Requirements for the JAFNPP Emergency Service Water System (46), is shown on the following two pages.
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safety-Related Functions:
Each train of the ESW System is required to supply raw water cooling to one train of the following safety-related loads:
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EDG Jacket Cooling Water Heat'Exchangers
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t Electric Bay Unit Coolers
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Control Room and Relay Room Air Handling Units
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j The Control Room chiller condensers and Crntrol Room ventilation
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l chiller condenser room air handling units were previously
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considered safety-related, but have since'been downgraded to non-
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All other.ESW loads not listed above are not safety-related.
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JAFNPP ENERGENCY SER WATER EQUIPMENT
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FLOW RATES AM CALCULATION REFEEL_ __S (ENNNY OPERATING MODE)
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CURRENT DESIGN BASIS
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NORNAL AS-NORMAL HEAT LAKE BUILT
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FLOW LOADS PER PER PER TEMP.
HEAT
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BASIS DUTY NOTES mummmmmmmmmmmmmm ---
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ESW FLOW N/A 625 1,250 2,9
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(TWO PER (GPN)
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TRAIN)
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t DUTY N/A 907,632 1,815,264
82 YES l
(BTU /
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ELECTRIC BAY 67UC-16A,B SW FLOW
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23 (A)
3,4,
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(GPN)
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25 (A)
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DUTY 294,000 156,070 156,070 3,4,
YES
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(BTU /
(A)
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33, HR.)
199,450-199,450
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CABLE TUNNEL 67E-11-SW FLOW 52.5 (11)
12 5,9
NO A
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67.8 (14)
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. DUTY 263,000 58,000 58,000 5,6,
NO B
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339,000
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(14)
i CRESCENT AREA 6600-22A'
SW-FLOW.
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TO K (GPN)
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DUTY 235,000
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588,655-7,8,
-82 YES C
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(A)
.- 36, HR.)
672,720
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(B)
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JAFNPP EMERGENCY SER WATER EQUIPMENT FLOW RATES AM CALCULATION REFERENCES (EMERGENCY OPERATING MODE 1
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CURRENT DESIGN BASIS
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NORMAL AS-NORMAL HEAT.
LAKE BUILT
FLOW LOADS PER PER PER TEMP.
MEAT
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DESCRIPTION COMPONENT SOURCE COMPONENT COMPONENT TRAIN REF.
BASIS DUTY NOTES i
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CONTROL ROOM 70AHU-3A,B GLYCOL-FLOW 101 110 110 10,
NO D
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I DUTY 449,000 213,000'
213,000
82 NO (BTU /
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RELAY ROOM 70AHU-12A,B GLYCOL FLOW
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DUTY 332,000 182,000 182,000
82 NO (BTU /
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NOTES:
A)
Normal. operating SWS flow is 4 'to 5 times. higher than emergency..
B)
-The 12 gpm set in Retrence 5 is assumed a-10*F water temperature rise. Based on the heat exchanger
actual design as assessed.in Reference 6, a much higher temperature rise can be expected, which means i
there-is considerable margin for increased heat load in the cable tunnels.
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C)
The 588,655 and 672,720
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BTU /Hr. heat loads shown are.only:that portion of the heat load required to be
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removed by the Crescent Area coolers. The Reference 7 and 8 analyses are transient computer models -
which: account for other heat sinks, but credit'the unit coolers for removing the above maximum heat loads. The actual heat loads 'are1784,000 and 875,000 BTU /Hr.,respectigy.
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D)
The 110 'gpa is the required ESW flow, these coolers normally operate on 101 gpa of glycol flow from.
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the chillers.
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' The 90'gpm is the required ESW flow, these coolers normally operate on 80 gpm of glycol flow from the
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a-chillers.
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A.
INSPECTION TEnMINOL0eY:
" FAILURE" AND
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" UNSATISFACTORY."'
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VISUAL INSPECTION CRITERIA.
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DIFFERED ~ YEAR-TO. YEAR'.
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TERMS ARE'USED TO DEFINE RESULTS l
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B.
SAFETY CONCERNSLMINOR -LWITH-REASONABLE-
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ASSUMPTIONS:- COOLERS ABLE TO PERF0nn
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SAFETY FUNCTION'IF REautRED i
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C.
CNECK VALVE ASME SECTION XI, IST~ PROGRAM HAS SEEN PREVIOuSLY APPROVEn On REVISEn i
ASNE.SECTION XI IST PROGRAM FIRST:
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INTERVAL (1977-1984)-
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FIVE (5) ESW/SWS DISASSEMBLY GROUPS.
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. APPROVED-BY NRC IN 1983.
l ASME SECTION XI'IST PROGRAM'SECOND
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INTERVAL, REVISION-0 (1985-1989)
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SAME PNILOSOPHY USED~FOR VALVE GROUPING.
TNREE (3) 0F FIVE- (5) FIRST INTERVAL GROUPSL CARRIED OVER.
O Two (2) NEw GROUPS ADDED BASED ON'
l FURTHER SCOPING: REVIEW.
SECOND INTERVAL NRC RAI RECEIVED REC 0004 ENDED REGROUPING : BY,' NRC -
l GENERIC LETTER 89-041 GUIDELINES.
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NRC DID'NOT' COMPLETE. REVIEW.-
ASME SECTION XI IST PROGRAM SECOND
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INTERVAL,' REVISION 1~(1990-DATE)
-FOURTEEN (14) GROUPS ESTABLISHED.-
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CONSISTENT WITH NRC GENERIC LETTER 89-04 GUIDELINES.
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CURRENTLY UNDERLREVIEW BY NRC: STAFF.
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A.
LER 88-009-01 fAPPEWIX E.11 l
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commEurs sinius 1.
Modification to provide permanent instrumentation to monitor crescent cooler thermal COMPLETE
performance.
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2.
Biweekly crescent cooler testing until modifications are completed.
ON-GOING l
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3.
Modify unit cooler fan and water controls to allow full water flow and cycle fan PENDIE and additional thermal performance instrumentation. Modification prior to start-up from
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1990 Refuel Outage. Completion date was delayed until September 30, 1990 (JPN-90-II).
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l Modification package is approved and issued for installation.
Installation imminent.
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B.
RESPONSE TO VIOLATION 88-17 - IMOPERABLE CRESCENT COOLERS (APPENDIX E.31 I
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l CtNnUTE NTs STATUS l
i 1.
Revise ST-19A to better measure cooler performance bi-weekly.
COMPLETE j
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Cooler cleaning and inspection.
COMPLETE i
3.
Reanalyze crescent cooler heat loads allowing operation up to 82*F service water COMPLETE
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temperature.
4.
Modify piping to reduce accumulation of suspended solids.
PEWING
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Larger mesh strainers.
COMPLETE 5.
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6.
Replace missing section of flanged pipe to UC-22J.
COMPLETE 7.
' Revise piping arrangement to UC-22D.
COMPLETE
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-Initiate performance testing of other service water-cooled safety-related heat COMPLETE exchangers.
i 9.
Accelerated test frequency for crescent area unit coolers maintained until performance ON-GOING l
trend indicates-they can be relaxed.
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B.
RESPONSE TO VIOLATION 88-17 - INOPERABLE CRESCENT COOLERS fAPPDWII E.31 (cont'd.)
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CONFETMS STATUS j
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10.
Review all Technical Specification surveillance requirements and ensure they are COMPLETE performed.
11.
Establish System Engineering Group (response to Flakt Report).
COMPLETE
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12.
Reorganize WPO Staff to assign to Nuclear Generation (response to Flakt Report).
COMPLETE i
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13.
Develop Modification Control Manual and Design Change Manual.
PARTIALLY
COMPLETE j
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14.
Develop formal root cause analysis program. July 1989.
PEISING f
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RESP 0MSE TO VIOLATION 88-23 - HIGf SERVICE WRTER TDFERATURE (APPU BIX E.31 i
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C9 NVIT M S STATUS i
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Revise FSAR to address 82*F lake temperatures. Safety evaluation is complete.
POSING l
Awaiting incorporation into revision.
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2.
Training of Engineering personnel on 10CFR50.59 safety evaluation preparation and COMPLETE I
importance.
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Streamline method for reviewing FSAR and other design issues that affect operability PENDING i
(JCO).
4.
Re-emphasize reportability requirements of 100FR50.72.
COMPLETE
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D.
ENFORCEMENT CONFERENCE fAPPElWIX E.2)
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C09 FETE RTS STATUS Comunitments contained in violation response (B) above with the following additions:
1.
Trend test data to establish testing and maintenance fr%r.cy to prevent flow CONTINUING restrictions.
2.
Feasibility and necessity of testing other safety-related coolers.
COMPLETE 3.
Administrative procedures describing the responsibilities and establishing the various COMPLETE channels to be utilized by the Systems Engineering Group.
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