ML20126M895
| ML20126M895 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/10/1985 |
| From: | Leech P Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8506200492 | |
| Download: ML20126M895 (22) | |
Text
{{#Wiki_filter:I June 10,1985 Docket No. 50-293 LICENSEE: Boston Edison Company (BECo) FACILITY: Pilgrim Nuclear Power Station
SUBJECT:
MEETING ON MAY 29, 1985 WITH BOSTON EDISON COMPANY REGARDING HYDROGEN WATER CHEMISTRY On May 29, 1985, a meeting was held with representatives of the Boston Edison Company (BECo) and the General Electric Company (GE) to learn the results of adding hydrogen to the Pilgrim reactor coolant during a test at the plant early in May 1985. Enclosure 1 is a list of the meeting attendees. Enclosure 2 provides copies of the viewgraphs presented by the BECo participants. During the test, hydrogen was added to the reactor coolant at various flowrates up to approximately 51 SCFM. The results indicate that injection of hydrogen at 15 SCFM is sufficient to reduce the oxygen concentration in the coolant to approximately 11 parts per billion (ppb). This meets a recommendation by GE that the oxygen concentration should be less than 20 ppb to mitigate crack growth in recirculation system pipes and nozzles. However, a further increase in hydrogen injection to approximately 23 SCFM was necessary to achieve a reduction of the reactor water conductivity to 0.100 S/cm, which is currently achieved at the Dresden plant. The test also showed that the main steam line radiation levels resulting from the above hydrogen injection rates of 15 and 23 SCFM were approximately 1.6 and 2.9 millirem per hour (mR/hr). The latter is nearly five times the level from operation without hydrogen addition. However, the higher level does not violate the present Technical Specifications. BECo is still considering whether a Technical Specification change is necessary for hydrogen addition during nonnal (i.e., other than test) operation. Radiation measurements taken in the turbine building and on the site during the test were higher than normal, as expected. These results will be used by BECo to determine appropriate mitigation measures. 8506200492 850610 PDR ADOCK 05000293 P PDR
BEco plans to install an electrolytic system to generate the hydrogen and oxygen necessary for improved hydrogen water chemistry prior to restart from the next refueling outage in the Fall of 1986. Conceptual information for its design is shown in the viewgraphs. Further details are expected
, later this year.
Original signed by/ Paul H. Leech, Project Manager Operating Reactors Branch #2 Division of Licensing
Enclosures:
As stated cc w/ enclosures: See next page
. DISTRIBUTION
$25 NRC PDR Local PDR ORB #2 Reading ORBf2 Mtg Summary File DVassallo PLeech OELD ELJordan BGrimes ACRS (10)
NRC Participants
/
DL:0RB . B#2 Pleech:'ajs DVassallo 06/10/85 06//g/85
- - =, . - - , . - - - . - . , - - - -
Mr. William D. Harrington Boston Edison Company Pilgrim Nuclear Power Station cc: Mr. Charles J. Mathis, Station Mgr. Thomas A. Murley Boston Edison Company Regional Administrator RFD #1, Rocky Hill Road Region I Office Plymouth, Massachusetts - 02360 U. S. Nuclear Regulatory Commission 631 Park Avenue Resident Inspector's Office King of Prussia, Pennsylvania 19406 U. S. Nuclear Regulatory Commission Post Office Box 867 Mr. A. Victor Morisi Plymouth, Massachusetts 02360 Boston Edison Company 25 Braintree Hill Park Mr. David F. Tarantino Rockdale Street Chairman, Board of Selectman Braintree, Massachusetts 02184 11 Lincoln Street Plymouth, Massachusetts 02360 Office of the Conmissioner Massachusetts Department of Environmental Quality Engineering One Winter Street Boston, Massachusetts 07108 Office of the Attorney General 1 Ashburton Place 19th Floor Boston, Massachusetts 02108 Mr. Robert M. Hallisey, Dire.ctor Radiation Control Program Massachusetts Department of Public Health 150 Tremont Street Boston, Massachusetts 02111 t
ENCLOS'JRE 1 ATTENDANCE LIST FOR MAY 29, 1985 MEETING WITH BEco ON HYDROGEN WATER CHEMISTRY AT PILGRIM STATION Name Affiliation P. H. Leech NRC/DL G. G. Whitney BECo
- 0. I. Ford GE C. Ferrell 'NRC/DE J. Klapproth GE J. W. Nicholson BEco L, C. Chan BEco E. F. Kearney BEco 4
i W. H. Koo NRC/DE V. Benaroya NRC/DE F. P. Felini GE J. E. Larsen GE R. J. Law GE H. F. Conrad NRC/DE
- J. J. McClellan BEco R. A. Hermann NRC/DL F. J. Witt NRC/DE M. Lamastra -
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i 1 i PROPOSED HYDROGEN WATER SYSTEM DESIGN PARAMETERS 1 A. HYDROGEN AND OXYGEN SUPPLY
- 1. ELECTROLYTIC GENERATION AT RATES THAT MATCH
, DEMAND,(STEAM OR FEEDWATER FLOW INDEX) - GENERATION CAPACITY - 50 SCFM - HYDROGEN - 25 SCFM OXYGEN
- 2. POSSIBLE MINIMUM GAS SUPPLY FOR 2 - 3 DAYS OF OPERATION
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i l . l B. COMPRESSION METHOD
- 1. THERMAL JET COMPRESSORS (NON-!GNIT!GN).
A. HYDF.0 GEN MULTI-STAGE TO 350-400 PSIG B. OXYGEN SINGLE STAGE T0 4TiiAN 10 PSIG
- C. INJECTION LOCATION
- 1. HYDROGEN - SUCTION OF REACTOR FEED PUMPS (3)
- 2. OXYGEN - 0FFGAS SYSTEM SUCTION OF AIR EJECTOR
- 3. OXYGEN - SUCTION OF CONDENSATE PUMP
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D. EQUIPfENT SHELTER
- 1. MODIFY EXISTING STRUCTURE AS SHELTER FOR GENERATION, POWER RECTIFIER AND BUILDING SERVICE ROOMS.
- 2. PASSIVE STRUCTURE DESIGN FOR GENERATOR ROOM A. FIXED OPEN INLET AND OUTLET VENTS B. BLOW-0UT PANELS AT 1 S0. FT. PER 30 CU. FT.
OF VOLUME - SET AT 25 PSI C. GAS TIGHT WALLS BETWEEN GENERATOR ROOMS AND OTHER ROOMS D. ACCESS FROM OUTSIDE ONLY E. VENTS FOR HYDROGEN AND OXYGEN F. FIRE PROTECTION SPRINKLER SYSTEM G. AREA MONITORING FOR llYDROGEN LEAKAGE
- __ - _ .- -- - -. _ _ . - _ . - . - _ . _ - . - . - _ = _ _ . _ - . -_ .._ - --
1 l 4
! E. CONTROL
] f1AIN CONTROL ROOM MANUAL / AUTOMATIC CONTROL STATION IN
; ADDITION TO RECORDERS, INDICATION ALARMS, EERGENCY SYSTEM SHUTDOWN SWITCH AND INSTRUCTION NECESSARY FOR I
REMOTE SYSTEM CONTROL. I i i 4 l I i
F. INSTRUPENTATION 1. ft)LTI-CHANNEL HYDROGEN MONITOR ALARM AT 1% AND AUTOMATIC
! SHUT 0FF AT 2%-
- 2. GAS CONCENTRATION AND STREAM CONTINUOUSLY MONITORED A. HYDROGEN AND OXYGEN PURITY IN STREAM B. OXYGEN CONCENTRATION IN OFFGAS
- 3. OXYGEN CONCENTRATION IN FEEDWATER, REACTOR RECIRCULATION AND MAIN STEAM SYSTEMS i
11 . HYDROGEN AND OXYGEM FLOW MEASUREPENTS l l t f f 1 i i
G. CODES AND STANDARDS
- 1. ASME BOILER AND PRESSURE VESSEL CODE, SECTIONS !!, VIII DIVISION 1, AND IX.
- 2. Af1ERICAN SOCIETY FOR TESTING F.ATERIALS (ASTM) STANDARDS
- 3. ANSI B31.1
- 4. NATIONAL ELECTRICAL CODE (NEC)
- 5. NATIONAL FIRE PROTECTION ASSOCIATION (NFPA) STANDARDS
- 6. TUBULAR EXCHANGER MANUFACTURERS ASSOCIATION (TEMA) STANDARDS
- 7. AMERICAN WELDING SOCIETY (AWS)
SPECIFICATIONS
- 8. AMERICAN INSTITUTE OF STEEL. CONSTRUCTION (AISC) STANDARDS
- 9. C0fiMONWEALTil 0F t1ASSACHUSETTS BUILDING CODE
\
H. ISSUES REQUIRING ANALYSIS / EVALUATION
- 1. THE EFFECT ON EFFLUENT RELEASES PER APPENDIX 1
- 2. THE EFFECT ON THE LittlTS OF 10 CFR 20
- 3. THE EFFECT ON RADIATION CONTROL PROCEDURES
- 4. THE EFFECT ON ALARA PROGRAM.
- 5. THE EFFECT OF INJECTING HYDROGEN INTO THE FEEDWATER SYSTEM WHICH COULD RESULT IN DISCHARGE OF FLUIDS TO SUMPS, PACKING LEAKAGE, HIGH POINT VENTS, ETC.
- 6. HYDROGEN GENERATION FOR THE FOLLOWING EVENTS:
A. PIPE BREAK B. SEISMIC C. TORNADO D. FIRE E. CONSTRUCTION ACTIVITIES F. TRUCK ACCIDENTS
- 7. OVERPRESSURIZATION, PURGING AND VENTING CONSIDERATIONS
- 8. EFFECTS ON REACTOR INTERNALS AND FUEL}}