ML20042G576
| ML20042G576 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/04/1990 |
| From: | John Nakoski NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20042G575 | List: |
| References | |
| NUDOCS 9005150099 | |
| Download: ML20042G576 (33) | |
Text
{{#Wiki_filter:r O i O U. S. NUCLEAR REGULATORY COMMISSION REGION I Docket No. 50-277 License Nos. DPR-44 Licensee: Philadelphia Electric' Company 2301 Market Street Fh11adelphia, Pennsylvania 19101 Facility Name-Peach Bottom Atomic Power Station - Unit 2 Meeting At: NRC Region I Office, King of Prussia, Pennsylvania Meeting Conducted: April 12, 1990 Prepared By: wA/. 6/fbo (JFhn Nakosk'i, Reactor Engineer Date Teactor Projects Section 2B Meeting Summary The status of Unit 2 emergency service water (ESW) and emergency cooling tower (ECT) design bases and operability were discussed. 9005150099 900507 gDR ADOCK 0500g'j7
9 Details I.D Meetino Attendees U. S. Nuclear Regulatory Commission W. Kane, Director, Division of Reactor Projects (DRP) l W. Hodges, Director, 01yi.sion of Reactor Safety (DRS) J. Durr, Chief. Engineering Branch, DRS R. Blough, Chief, Projects Branch No. 2, DRP i P. K. Eapen, Chief, Special Test Programs Section, DRS D. Florek, Senior Operations Engineer, BWR Section, DRS J. Lyash, Senior Resident Inspector-R. Urban, Resident Inspector-J. Trapp, Senior Reactor Engineer, STPS, DRS J. Nakoski, Reactor Engineer, Reactor Projects Section 28, DRP G. Suh, Project Manager, NRR P. Koltay, Senior Inspector, Special Inspections Branch, NRR Philadelphia Electric Company C. McNeill, Executive Vice President-Nuclear D. Smith, Vice President, Peach Bottom D. Helwig, Vice President Nuclear Services J. Franz, Plant Manager, Peach Bottom D. Meyers, Superintendent, Technical Support - Peach Bottom A, Fulvio, Technical Engineer, Peach Bottom J. Basilio, Licensing Division, Peach Bottom G. Beck, Nuclear Engineering Division J. Hafnagel, Nuclear Engineering Division W. Dobson, Nuclear Engineering Division G. Reid, Nuclear Engineering Division Delmarva Power and Light Company H. Buddenbohh Atlantic, Electric Com m H. Abendroth Commonwealth of Pennsylvania S. Maingi, Nuclear Engineer, Bureau of Radiation Protection i e 9 k
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2.0 Purpose and Scope
of the Mee_ ting n At the request of the licensee a meeting was held in the NRC, Region I office to discuss the status of the emergency service water (ESW) system operability for Peach Bottorn Unit 2 and dual unit operation. In addition discussion was held on the emergency c.ooling tower (ECT) system design bases. The licensee presented their evaluation of the operability of the ESW system for Unit 2 and dual plant operation. The licensee discussed the testing methods and test results obtained in evaluating ESW system i operability. During the meeting the licensee commited to: 1) enhanced surveillance testing of the Unit 2 emergency core cooling system (ECCS) unit coolers until the scheduled ESW piping replacement is complete;
- 2) review and revision of applicable procedures based on the results of 1
the ESW system testing; 3) performance of one internal SSFI completed by the end of 1990 and two additional internal SSFIs completed during 1991; and 4) complete a screening of other systems for similar problems by May 1990. During the presentation an error in the presentation was noted in that the action in response to Generic Letter 89-13 will not be implemented by April 1991, but by the date specified in PEco's response to Generic Letter i 89-13. l No additional concerns or questions were identified by NRC regarding ESW system operability for Unit 2 restart. A summary of the licensee's presentation is attached with this report as Attachment I l l l i =
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7 i p"" %v e e(Ex@ll@ce)% L 8 l 0WER STA7\\O j l l l PEACH BOTTOM UNITS 2 & 3 PRESENTATION TO NRC L APRIL 12,1990 ii j* [ i --.....__........,,........_........,...-_.._.__._,_...,....__.._.,,.,.._.,_,_s
f j s ji ?- = i 1 AGENDA 1 i t 1. INTRODUCTION - D.M. SMITH i B 7 a s... L LWil. EMERGENCY SERVICE WATER SYSTEM - W.L. DOBSON l s k a i-. h 111. EMERGENCY COOLING TOWER - D.R. MEYERS~ I l + ) IV. TECHNICAL STAFF USE of PROCEDURES - D.R. MEYERS j i V. ROOT CAUSE EFFORT and POTENTIAL j GENERIC IMPLICATIONS - G.J. BECK d i
PEACH BOTTOM ATOMIC POWER STATION UNITS 2&3 ESW SYSTEM OPERABILITY II. ESW Systems A. Description of Problem B. Realignment of ESW C. Test Results D. ESW Surveillancs Testing E. Future Plans 4
e. EMERGENCY SERVICE WATER PEACH BOTTOM ATOMIC POVER STATION t t A A A A A A A 1 x x x x x 6 Y Y fY,Y ff,Y f',Y Y Y 1 1 4 4-x
- A* RHR C* RHR B*RHR v RHR H
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510 Unit 2 Turbine B1dg Unit 3 Turbine Bldg i
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j$gqr jf D o_ DG Co SERVICE HPSW ESW -
ESV HPSW SERV 1CE WATER
- WATER SLU1CE GATES SLUltE GATES l
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A. Description of Problem Adequacy Of Surveillance Testing - Reportable Evaluation Form - Corrective Action Report - SSFI Team Unit 3 Testing to Support JCO Unit 2 Testing Showed inadequate Flow s
t i i B. Realignment of ESW -l Ob.ective: - Increase Unit 2 Room Cooler Flow - Maintain Unit 3 Flow Margin 1 l input to Decision: I - Large Flow Margin to D/G 1 - Unit 2 ESW Pipe Replacement Schedule e l - Room Cooler Design Basis 1 l Realignment Of ESW - Throttle D/G ESW Flow 1 - Valve Out One Unit 2 ESW Room Cooler Per Room i l ~ L
0 ) i.- i i C. Test Results i ESW Ooerability Test Method
- 1. Dual Unit Test Lineup
. Design Basis Lineup - Record ESW Ring Header Pressures & Flow. l
- 2. Unit 2/3 Component Test Lineup Design Basis Lineup On One Unit Service Water Throttled
- Measure Flows in Room Coolers i 1 'I d f N ~ w- _y.. .r. p
_.. _ _ _.. ~... _ _.. _. _ _..... _ _... _. _. 1.- C. Test Results Unit 3 JCO Test Results Unit 2 Test - Full D/G Flow & Single Cooler Per Room Unit 2 Test -Throttled D/G Flow & Single Cooler Per Room l l l l 4 1 l b
F-A I ESW Operability Testing - Unit 3 Data Point 'B' Flow Results (a P=19 psid) Seal Water-Pump Pump Room Cooler Req. Flow UT Margin Above Cooler Flow (gpm) (gpm) Req. Flow 4.0 ppm req. Pressure: (psid) (psid) 'A' RHR 3A 30.4 60.0 97.4 % 9.1 U/3 Ring Header Supply 30 28 38 30.4 69.0 127.0% U/3 Ring Header Retum 9 9 'C' RHR 3C - 30.4 68.0 123.7 % 12.7 Minimum U/3 AP 19 3D 30.4 63.0 107.2% 'B' RHR 3E 30.4 65.2 114.5 % 6.6 3F 30.4 62.8 106.6 % 'D' RHR 3G 30.4 69.7 129.3 % 9.0 3H 30.4 40.8 34.2 % 'A' Core Spray 3A 13.3 19.8 48.9 % 38 13.3 26.3 97.7% Motor Oil 'C' Core Spray 3C 13.3 32.2 142.1 % Cooler 3D 13.3 22.9 72.2 % Test 'B' Core Spray 3E 13.3 17.4 30.8 % Perform 3F 13.3 26.4 98.5 % Satisfactory { 'D' Core Spray 3G 13.3 22.2 66.9 % l 3H 13.3 23.1 73.7 % j HPCI 3A 23.2 30.3 30.6 % 3B 23.2-28.0-20.7 % RCIC 3A 20.0 24.1 20.5 % 3 3B 20.0 25.0 25.0 % j - TOTAL 218.0 418.8 92.1 % 3 -f l 4 4 '~
. -~~. ESW Operability Testing Singla Room Cooler - Unit 2 I Data Point
- B' Pump 'A' Pump Flow Results- (AP-11.0 psid) 30-Mar 30-Mar Room Cooler Req. Flow Bucket Margin Above j
(gpm) (gpm) Req. Flow f, Pr ssure: (psid) (psid) 'A' RHR 2A 30.4 l Minimum U/2 AP ,11 2B 30.4 37.0 21.7 % 'C' RHR 2C 30.4 48.6 59.9 % Minimum U/3 AP 16.5 2D 30.4
- B' RHR 2E 30.4 56.0 84.2 %
Flow: (gpm) (gpm) 2F 30.4 U/2 Ring Header 414 395 'D' RHR 2G 30.4 50.0 64.5 % 2H 30.4 E1 D/G 1082 1148 'A' Core Spray 2A 13.3 16.0 20.3 % i E2 D/G 976 1026 28 13.3 E3 D/G 934 1015 'C' Core Spray 2C 13.3 16.0-20.3 % E4 D/G 1015 1052 2D 13.3 l 'B' Core Spray 2E 13.3 18.0 35.3% 2F 13.3 5 'D' Core Spray 2G 13.3 22.5 69.2 % 2H 13.3 - HPCI 2A 23.2 34.0 46.6% (j -28 23.2 9 . RCIC 2A 20.0 2B 20.0 23.4 17.0% TOTAL 218.0 321.5 47.5% i P 4 i. f
ESW Operability Testing With D/G Throttled and Single Room Cooler - Unit 2 ?. Data Point
- B' Pump 'A' Pump Flow Results (AP=13.5 psid)
Room Cooler Req. Flow Bucket Margin Above (gpm) (gpm) Req. Flow Pressure: (psid) (psid) 'A' RHR 2A 30.4 Minimum U/2 AP 13.5 2B 30.4 45.0 48.0% C RHR 2C 30.4 54.5 79.3 % Minimum U/3 AP 22 2D 30.4 'B' RHR 2E 30.4 64.3 111.5 % Flow: (gpm) (gpm) 2F 30.4 U/2 Ring Header 443 409 U RHR 2G 30.4 60.0 97.4 % 2H 30.4 E1 D/G 710 715 'A' Core Spray 2A 13.3 19.1 43.6 % E2 D/G 722 728 2B 13.3 E3 D/G 715 750 'C' Core Spray 2C 13.3 19.0 42.9% E4 D/G 709 687 2D 13.3 'B' Core Spray 2E 13.3 23.0 72.9 % 2F 13.3 'D' Core Spray 2G 13.3 22.5 69.2 % 2H 13.3 HPCI 2A 23.2 39.7 71.1 % 28 23.2 RC!C 2A 20.0 2B 20.0 26.5 32.5% TOTAL 218.0 373.6 71.4 % 9 y .,1 .~ ,.,.-._,_.___e__
Data Evaluation And Conclusion UNIT 2 Minimum Flow Requirements are Met With Margins Ranging From 17% to 112%. - All Unit 3 ESW Load Aligned - With or Without D/G Flow Throttled - Single Cooler Per Room Operation UNIT 3 Unit 3 Ring Header AP is Greater Than the AP l Measured During the Successful Unit 3 Operability l Test Supporting the JCO. ~ - Aligned With Unit 2 - D/G Flow Throttled CONCLUSION l It Has Been Demonstrated That the ESW System Can meet its Design Performance Requirements With Two Units in Operation. ? ~.. -,,, - , ~ -, _. - - -,.. ~ ,. -.... _ ~.
l D. ESW Surveillance Testing Operability Testing Key Measured Parameters Testing Method i Data Trending 1 1 I. I l l 4 w y, ...-..s ,p.,y, y.,,. _ _ .y,, ,.,se,.s, y.,_ y,
..____m.___ i .. Operability Testing 1 ESW Pump Valve & Flow Surveillance Test l l ESW Component Surveillance Flow Test: l - Room Cooler - RHR Seal Water Cooler L ESW Design Line-up Flow Surveillance (Dual Unit) - - Core Spray Motor Oil Cooler Surveillance Test i e ? t p-y w w --*+-9 s e ,.-.y-,, w=--' 6
r i Key Measured Parameters ESW Pump Vave & Flow Surveillance Test - - 4 -- Disch, Pressure River Level I - Vibration (Pump) - Amps - Check Valve Opening ESW Component Surveillance Flow Test: - Room Cooler Flows - RHR Seal Water Cooler Flows . Room Cooler AP-m "' ' - Ring Header A P (supply to return) I ESW Design Line-up Flow Surveillance (Dual Unit) - Ring Header Flow on Both Units 1 - Ring Header AP (supply to return) - Diesel Generator Flows. Core Spray Motor Oil Cooler Surveillance Test - Oil Temperature - Cooling Water inlet and Outlet Temperature l-g y r
e Test Methods Room Cooler Flows - Bucket Testing - Ultrasonic . Ring Header Flows - Ultrasonic ,1 l Core Spray Motor Oil Cooler Flows-l - Oil Bath Temperature l - ESW Inlet & Outlet Temperature - Perform Heat Transfer Calculation Under. Design Conditions l Diesel Generator. Flows - Ultrasonic L Pump Vibration Testing l - Velocity Meters I k
n 0' L. Data. Trending - 1 i f Plant Performance Monitoring Program - System Engineer-Maintains System Data I o .i I l i l l .l 1 l 1 'i i -j i l 4 ( i
-_. -n y- - x l E. Future Plans 1 L t L ~ i L Unit 2 Modification 5046 t L 1 L - Scheduled for Cycle 8 l - Replaces ESW Ring Headers and Room Piping - Add Design Enhancements Relocation of ring headers l Segmentation of. ring headers L Throttle valves- ~~ - Continuous flow through all branch lines Pipe clean-outs Flow measurement provisions 1 l k 4 1 ..-.1, _t .,e-...
i l i Generic Letter 89-13: Implementation by April 1991 1 -Action I: g Trending of' intake structure PM program. . 1 Chemical treatment improvements. j Flushing and lay-up practices. -Action ll: l Heat transfer. testing program. -Action-lil: ~~ Piping inspection and maintenance. -Action IV: Design basis document for ESW & HPSW.. i l -Action V: l Review procedures and training involving ESW & l l HPSW. i 4 i
m e c F EMERGENCY COOLING TOWER ECT VERIFICATION ESW BOOSTER PUMP i l PROCEDURAL GUIDANCE i A 7 ) j l c i i i I h w se e v y w. w. <w 9 mg.ye. ,j -., =.g-w,.-.g .m. m oes we- ,--%...w. ..,-y 4 e, e e-
a ECT NORMAL HEAT SINK UNAVAILABLE o SAFETY DESIGN BASIS - NONE o NEGOTIATED REQUIREMENTS. o DESIGN'- SEISMIC', LOOP - o NOT A SAFETY SYSTEM' nu: #: c -~r o o MEETS DESIGN CRITERIA OF FSAR.- s + i i. i e i y
ECT TESTING DATA FOR PROCEDURAL GUIDANCE-o ESW BOOSTER PUMP DISCHARGE ESW OPEN LOOP o - ESW TO ECT i i ECW. CLOSED LOOP o 1 i l i 1 - i f 1 4 ~m, ,-gn, -r ye ne ~,.,., pcr-we,- ,,,e,~--- --,,,g-7 ,,.-* g *M e e ,,,w ,.,w a _+m-ea,
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j v L SAFETY EVALUATION. l ESW. BOOSTER PUMPS L t s o: ACCEPTABLE NPSH L CORRELATION OF THROTTLING o - SYSTEM FLOW l . PUMP SUCTION l. t-t I - t 9 4 r- .. i ..,.....-........,-.aa.-..
.. = =.=.=_.. - - ~ - -; o 1 b t. lESW/ECT 1 i PROCEDURES t L o SO 48.1.B i j - ESW BOOSTER PUMP DISCHARGE: l - MONITORING l APPRdPRIATE ACTIONS j. m:n - - - -~ q l OTHER PROCEDURES o i - i ) g ..y --e-- e + w .,--c.e-, ,,e-. e---.
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j i -j TECHNICAL STAFF .l PROCEDURAL i ISSUES i i. i [ o INSUFFICIENT UNDERSTANDING (SSFI) o HISTORICAL INFLUENCE \\ L o VERBATIM PROCEDURAL COMPLIANCE i {. l f i l
l t 6 r t. i o POSSIBLE CAUSES 4 l- - lNATTENTION TO DETAIL' - AUTHOR L - KNOW MORE THAN AUTHOR. j - UNCLEAR EXPECTATIONS \\ k e G p I i l l I. l ll l 4 h
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- EVOLVING UNDERSTANDING OF DESIGN BASIS REQUIREMENTS
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.,(,....- SCREENING CRITERIA 1 l o Il e i e,1 e d .- Q-LISTED' SYSTEM OR? SUBSYSTEM d . UNIQUE DESIGN-b PRA IMPORTANT r o i-l -' i t 3 1 ( r l 'l l ~! !~ l l I I ~i L 1 l 1
L.-{..: - CON CLUSION-I p. . SHORT. TERMLACTION = INTERNAL SSFl FOR HPSW-F i LONG TERM ACTION y, .. !') 2 lNTERNAL SSFI'S-lN 1991 1 q } REVIEW DBR PRIORITY. n USING SCREEN ~ CRITERIA l j I. 1 l Y c_ _- 11}}