ML18153C332
| ML18153C332 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/02/1990 |
| From: | Merschoff E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 9008210186 | |
| Download: ML18153C332 (19) | |
Text
August 2, 1990
Mr. W. L. Stewart Senior Vice President - Nuclear 5000 Dominion Boulevard Glen Allen, VA 23060 Gentlemen:
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SUBJECT:
.MEETING
SUMMARY
FOR RECIRCULATION SPRAY HEAT EXCHANGER (RSHX)
PROPOSED TESTING This letter refers to the RSHX proposed testing meeting held at our request on July 24, 1990.
This meeting concerned activities conducted at your Surry facility.
A list of attendees, a summary, and a copy of your handout is enclosed.
In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosu~es wi 11 be pl aced in the NRC Public Document Room.
Enclosures:
- 1. List of Attendees
- 2.
Meeting Summary
- 3.
Handout cc w/encls:
E. W. Harre 11 Vice President - Nuclear Operations Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 J. P. O'Hanlon Vice President - Nuclear Services Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 (cc w/encls cont'd - See page 2) 9008210186 F'DR ADCIU,::
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- ~100::::02 (l~'.0002:30 F'DC Sincerely, Original signed by Ellis W. Merschoff Ellis W. Merschoff, Acting Director Division of Reactor Safety
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Virginia Electric and Power Company 2
(cc w/encls cont'd)
M. R. Kansler
.. Station Manager Surry Power Station P. 0. Box 315 Surry, VA 23883 R. F. Saunders, Manager Nuclear Licensing Virginia El~ctric & Power Co.
5000 Dominion Boulevard Glen Allen, VA 23060 Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, VA 23683 W. T. Lough Virginia Corporation Commission Division of Energy Regulation P. 0. B6x 1197 Richmond, VA 23209 Michael W. Maupin Hunton and Williams P. 0. Box 1535 Richmond, VA 23212 C. M. G. Buttery, M.D., M.P.H.
Department of Health 109 Governor Street Richmond, VA 23219 Attorney General Supreme Court Building 101 North 8th Street Richmond, VA 23219 Commonwealth of Virginia (bee w/encls - See page 3)
August 2, 1990
Virginia Electric and Power Company bee w/encls:
Document Control Desk NRC Resident Inspector U.S. Nuclear Regulatory Commission Route 1, Box 166 Surry, VA 23883 NRC Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 78-A Mineral, VA 23117 E. Merschoff P. Fredrickson G. Belisle s. Ebneter J. Mi 1 hoan L. Reyes M. Sinkule 3
RII~
PF~dr~ ckson owe~
August 2, 1990
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ENCLOSURE 1 List of Attendees U. S. Nuclear Regulatory Commission E.W. Merschoff, Acting Director, Division of Reactor Safety (DRS)
G. A. Belisle, Chief, Test Programs Section, Engineering Branch, DRS B. C. Buckley, Surry Licensing Project Manager S. A.. Tingen, Surry Resident Inspector Virginia Electric and Power Company (Virginia Power)
E.. R. Harrell, Vice President, Nuclear Operations W. R. Benthall, Supervisor, Surry Licensing R. P. Cherry, Engineer, Nuclear Licensing and Programs A. W. Hall, System Engineer, Surry F. W. Hartley, Consultant J. P. Maciejewski, Manager, Nuclear Quality Assurance J. A. Price, Assistant Station Manager, Nuclear Safety and Licensing
- R. L. Rasnic, Supervisor, Mechanical Engineering C. M. Robinson, Jr., Manager, Civil/Methanical Engineering R. F. Satinders, Manager, Nucle~r Licensing and Programs D. A. Sommers, Supervisor, Corporate Licensing (Surry)
J. D. Waddill, Engineer, Mechanical Engineering J. L. Wilson, Assistant Vice-President,. Nuclear Operations
ENCLOSURE 2 Meet i n*g Summary e
On July 24,
- 1990, representatives from Virginia Power met with the NRC at the corporate office in Innsbrook.
Virginia Power gave a presentation (Enclosure 3) on their RSHX service water flow testing.
The presentation delineated which RSHXs were to be tested, the test duration, the impact on the operating unit, the service water operational configuration, the test alignments and data to be taken, the instrumentation location, and various macrofouling concerns and their resolution.
After the presentation, there was a question and answer period where NRC concerns were addressed.
During this period, the NRC requested a copy of the calculations that were performed to verify that the RSHXs selected for testing were representative of all RSHXs for Unit 1 and Unit 2 and the procedure for testing the RSHXs when it was completed.
Virginia Power stated that th_e calculations and test procedure _would be provided for review* when they were completed.
Additionally, a concern was expressed that data was not presented to show that th~ proposed 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test duration was sufficiently long to provide results that could be reliably extrapolated over the required 30 day period.
Virginia Power agreed to validate the proposed extrapolation methodology using empirical dat~ from the component cooling water system and provide this basis for test duration to the NRC for review.
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ENCLOSURE 3 VIRGINIA POWER RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER.FLOW TESTING
~ ~ - -
SURRY UNIT 1 RSHX TEST
- TEST WILL USE ONE SW HEADER: 36-WS-21-10
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- A 0.2 PSI MAXIMUM DIFFERENCE IN SW PRESSURE DROP AT RATED FLOW FOR
. THE 8 RSHXs (CALCULATION ME-260)
- SYSTEM CONFIGURATIONS ARE NEARLY IDENTICAL PHYSICALL V AND ANALYTICALLY
- SELECTION OF HEADER BASED ON MINIMIZING INSTRUMENTATION CABLE RUNS
SURRY UNIT 1 RSHX TEST.
- OPERATING UNIT IMPACT
- sw~103-C AND O VALVES PLACED IN ADMINISTRATIVE CONTROL BASED ON
.. INVENTORY REQUIR.EMENTS
- CW VALVE MANIPULATIONS CONTROLLED TO MINIMIZE TRANSIENTS
- LIQUID WASTE HOLD-UP REQUIRED
- - CCHX FLOW MONITORING POTENTIALL V REQUIRED
SURRY UNIT 1 RSHX TEST
- OPERATING UNIT IMPACT
-, SW-103-C AND D VALVES PLACED IN ADMINISTRATIVE CONTROL BASED ON
. INVENTORY REQUIREMENTS
.- CW VALVE MANIPULATIONS I
CONTROLLED TO MINIMIZE TRANSIENTS
.. LIQUID WASTE HOLD-UP REQUIRED
- CCHX FLOW MONITORING POTENTIALL V
- REQUIRED
- TEST CONFIGURATION AND PROCEDURE
- SYSTEM WILL BE TESTED IN OPERATIONAL
. CONFIGURATION ON SW SIDE
- SYSTEM WILL BE FILLED PRIOR TO INITIATING FULL FLOW TO PROTECT TEST INSTRUMENTATION I
- CW WILL BE FLOWING BUT WILL BE ISOLATED DURING TEST
- CW DISCHARGE TUNNEL VACUUM BREAKER WILL BE OPENED
- SYSTEM FLOW MA V BE ADJUSTED TO DESIGN VALUES USING 105 VALVES*
TEST. CONFIGURATION AND PROCEDURE
-* * (CONTINUED)
- . NORMAL TEST ALIGNMENT IS fLOW THROUGH I BOTH B AND C RSHXs (MINIMUM FLOW)
- AT ABOUT 4 TO 6 HOUR INTERVALS, FLOW WILL BE ALIGNED TO B ONLY THEN C ONL V (MAXIMUM FLOW)
.. DATA RECORDED DURING TEST FOR.EACH RSHX
- - FLOW RATE (ACCURACY:.2°/o).
- INLET PRESSURE {A*CCURAcv*: 1 INCH WATER)
- - PRESSURE DROP (ACCURACV:* 1 INCH WATER)
-. CANAL LEVEL ON TREND RECORDER (ACCURACY: 1 INCH WATER)
- e
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TEST CONFIGURATION AND PROCEDURE (CONTINUED)
- LOCATIO.N OF INSTRUMENTATION
- INLET STATIC PRESSURE: UPSTREAM OF 104 VAL VE LOCATION
- FLOW RATE: IN SPOOL-PIECE REPLACING 104 VALVE AND EXPANSION JOINT {MINOR CHANGE IN SYSTEM ANAL YT!CALL V MODELED)
~ OUTLET STATIC PRESSURE: UPSTREAM OF 105 e
- VAL VE LOCATION
- . TEST SURPASSES PRE-OP TEST IN ACCURACY,-
DURATION, INTEGRATION OF DATA AND RECONCILIAT-ION WITH ANALYTICAL BASES
MACROFOULING CONCERNS
- INDUSTRY AND SITE MACROFOULING CONCERNS HAVE LED TO QUESTIONS ON MACROFOULING IMPACT ON THE RSHXs
- GENERIC LETTER 89-13.
- CCHX AND MAIN CONDENSER OPERATING EXPERIENCE
- DECREASE IN ACCIDENT HEAT LOAD OFFSETS EXPECTED PROGRESSIVE FOULING OF THE RSHXs
- DESIGN BASIS (UFSAR SECTION 6.3.1.4)
MACROFOULING CONCERNS (CONTINUED)
I I
- TEST DURATION (24 HOURS) IS SUFFICIENT TO ESTABLISH MACROFOULING*TREND e
- HEAT REJECTION REQUIREMENTS DECREASE RAPIDLY
- MACROFOULING SHOULD BE MEASURABLE IN 24 HOUR PERIOD OR IT IS OF LIMITED CONSEQUENCE TO RSHX HEAT REJECTION
- EXPECTED TEST FLOW*RATE WILL FLOW VOLUME OF WATER UPSTREAM OF BAND C RSHX TO INT AKE TRASH RACKS IN LESS THAN 1.5 MINUTES.
- SEASONAL CORRECTION OF MACROFOULING EFFECTS CAN BE MADE us1*NG CCHX DATA
MACROFOULING CONCERNS (CONTINUED)
- OPTIONS ARE AVAILABLE FOR LONG-TERM COOLING
- IT IS LIKELY THAT A MINIMUM OF 3 RSHXs WILL BE AVAILABLE FOR LONG-TERM COOLING
- ACCEPTANCE CRITERIA: MINIMUM SAFEGUARDS MAINTAINED FOR 30 DAYS.
- HEAT REJECTION CAPABILITY OF 2 RSHXs (ANY COMBINATION) MEETS OR EXCEEDS ACCIDENT HEAT LOAD.
SUMMARY
- RSHX TEST OF 2 OUT OF 4 HEAT EXCHANGERS IS ADEQUATE TO CONFIRM>UNIT 1 -DESIGN CAPABILITY, UNIT 2 IS ANALYTICALLY SIMILAR TO UNIT 1
- GENERIC LETTER 89-13 PIPING INSPECTIONS -
ASSURES NO MACROFOULING/FLOW -
OBSTRUCTIONS EXIST IN THE NON-TESTED PIPING
- MACROFOULING TRENDS WITH SEASONAL CORRECTIONS WILL BE ESTABLISHED BY THE TEST
- DESIGN BASIS OF THE RSHX WILL BE CONFIRMED
- FOR BOTH HEAT TRANSFER AND INVENTORY CASES
A
. lA A
B D
10
- INTAKE CANAL MDV-SW
. 103 -
. MDV-SW 104 RECIRCULATION COOLERS.
MDV-SW 105.
-18,
B DISCHARGE TUNNEL TO SEAL PIT e TO RADIATION MONITORING SYSTEM.
D C
lC SERVICE WATER SUPPLY.TO RECIRCULATION COOL.ERS DETAIL
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RSHX HEAT REMOVAL CAPACITY 60 50 3:
- E -
40 UJ m
HEAT ADD
- c 30 HEAT REMOVAL
,c 0
UJ Q
20 e
10 0 -l,.....-----------,,------------,-----r----....----r----T""""'."'-----,
0 200 400 600 800 TIME (HOURS)
RSHX HEAT REMOVAL CAPABILITY 60 4
e 50 3::
a HEAT ADD HEATRE~VAL w
40
- c 0 w C
30 20 0
1 0 20 30 TIME (HOURS)