ML20128F265
| ML20128F265 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/28/1985 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Harold Denton, Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 2NRC-5-095, 2NRC-5-95, NUDOCS 8507080189 | |
| Download: ML20128F265 (7) | |
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'Af 4 ) 78 -5 41 (412)923-1960 Nuclear Construction Division Telecopy (412) 787-2629 Robinson Plaza, Building 2, Suite 210 Pittsburgh, PA 15205 June 28, 1985 Mr. Harold R. Denton Of fice of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. George W. Knignton, Chief Licensing Branch 3 Of fice of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Regulatory Guide 1.97 Implementation Report REFE RENCES : 1) NRC Letter, George W. Knighton (NRC) to John J. Carey (DLC),
" Beaver Valley Unit 2, Requests for Additional Information -
Conformance to Regulatory Guide 1.97," dated April 13, 1985
- 2) Duquesne Light Company" Letter (2NRC-3-072), E. J. Woolever to H.
R.
Denton, NRC, Regulatory Guide 1.97 Implement at ion Report," dated September 12, 1983 Gentlemen:
Reference 1 above, received on May 2, 1985, provided Duquesne Light on the Beaver Valley Power Station Company ((DLC) with the NRC interim report Unit 2 BVPS-2) Regulatory Guide L.97 Implementation Report (Reference 2).
Attachments 1, 2, and 3 of this letter provide the DLC responses to comments contained in the NRC interim report in accordance with the NRC req ue s t ed submittal schedule.
These res pons es were discussed with the NRC at a June 18, 1985, informal meeting held at the DLC Bethesda P roj ect Office.
The info rmat ion prov ided in the attachments will be utilized to update Section 7.5 of the Final Safety Analysis Report.
If there are any questions in this regard, please contact Mr. Curtis L.
Hill, Senior Project Engineer, Regulatory Af fairs Department, at (412) 787-5141, extension 145.
DUQUESNE LI HT COMPANY
/
By J4/.y. Carqy Vie 6 President KEW/wjs Attachments Mr. B. K. Singh, Project Manager (w/a) cc:
Mr. G. Walton, NRC Resident Inspector (w/a)
NRC Document Control Desk (w/a) gg73d Mg2 i i F
ATDOMNT 1 OMENT NO.
IMPIDEN-(INEL QUALIFICATIm tGGER OF LtOICAIm TATION POER ONCWSION)
VARIABE RAtCE/ STATUS 1YPE/ CATEGORY ENVIlOHNTA1.
SEISMIC OWHIS DEVIG DATE SUPPLY (DGORMAN 10 - 6 0
CPS B1 Yes Yes 2
2 plasma Fuel loal 1
Neutron Flux 10-410 200% of displays IE Yes l
pow r i recorder 2
Contabrent area See FSAR Tab 1e 7.5-1 Amendment 9
December 1984 radiation level (high rarge) 3 Plant wrt rali-See FSAR Tab 1e 7.5-1 Amendment 9
December 1984 and ation level Note 1
4 Site environ-For range / status see note 2; other information mertal ralia-provided in FSAR Tab 1e 7.5-1 tion level 5
Acetmulator See Note 3; other information provided in FSAR tank level ani Tab 1e 7.5-1 pressure 6
Acctm11ator Open/ Closed D2 Yes Yes 1 per i pair of Fuel load IE Yes(4) isolation valve valve lights per position valve 7
Reactor coolant 0-1200 ATs D3 lb No 1 per 3 meters Fuel loal Non IE Yes ptunp status ptrop 8
Pressurizer See Note 5 and pressurizer heater power avai1-heater status abi1ity in FSAR Tabie 7.5-1 9
Quench tank 0-100%
D3 No No 1
M:ter Fuel loal Non IE Yes level 10 Quends tank 50*-350*F D3 tb lb 1
Meter Rel loal Non IE No(6) temperature Il Quench tank 0-120 psig D3 No No 1
Meter Fuel loal Non IE Yes pressure 12 Stean generator See Note 7 level
QKEdr ND.
DFIDEN-(INEL QUALIFICATIm 10MIER OF D01CAltR TATim POER Q]NCWSION)
VARIAME RAtGE/ STATUS IYPE/CATE00lE ENVIIO tfNEAL SEISMIC QWNELS DEV1 DATE SUPPLY 0[tGDRMAN L3 Cortairmert.
0-200*F D3 tb lb 20 Canputer Fuel loal Non IE tb(8) atmosphere or tkter tunperature 14 Coid.ainnent See note 9 D2 Yes Yes i2 2 meters Fuel loal IE tb(9) sunp water tunperature 15 Liquid waste 0-150 indles D3 tb tb 1 per 2 meters Ebel loal !bnIE Yes tark level tank 16 Ralioactive 0-100 psig D3 No tb l per Caputer Fuel loal Non IE tb(10) gas Iuldup tark tank pressure 17 Condenser air See Note 1L and FSAR Tab 1e 7.5-1, Amendment 9
runoval systen December 1984 exhaust l
18 Stean line 10-2_tg3 E2 Yes Yes 1 per 1 indica-Fuel loai Non IE Yes nonitor uCi/cc loop tion per loop 19 Particulates See Note 12 ani halogens 20 Airborne ralio-See Note 13 halogens and particulates see Note 14; other information 21 Plant ani For range / status, environs provided in FSAR Tabie 7.5-1 under site environ-raiioactivity menta1 radiation 1 eve 1 conplete IbnIE Yes 22 Wini direction 0-360*
E3 tb tb none reconfer 1
23 Plart ard See Note 15 environs raliAtion
ATTACHMENT 2 NOTES l.
PLANT VENT RADIATION LEVEL - FSAR Section 6.5.3.2.3 discusses how the ventilation system diverts into the elevated release stack located on top of the Containment Building.
Equipment provided on the elevated release collects and detects particulates, collects iodine, and detects nobel gases in accordance with Regulatory Guide 1.97 criteria.
2.
SLTE ENVIRONMENTAL RADIATION LEVEL - Reference is made to FSAR Table
- 1. 9 -2 for BVPS-2 dif ferences from SRP No.
i 12.3-12.4, " Radiation Protection Design Features."
This table contains the BVPS-2 position regarding use of po rt ab le radiation monitors. Attachment 3 Lists the type and range of portable and laboratory radiation mnitors to be used at BVPS-2.
The range of this ins t rument at ion meets the guidance criteria in Reg. Guide 1.97.
In addition, FSAR Table 12.3-10 lists the permanently installed area radiation monitors along with their location and range. This instrumentation meets Category 3 recommendations of Reg. Guide 1.97.
3.
ACCUMULATOR TANK LEVEL AND PRESSURE - Regarding accumulator tank leve l, ac cumulato r isolation valve pos it ion (2SLS*MOV865 A, B, and C) and RCS pressure (WR) provide the operator adequate information to monitor the operating status of the accumulator during potential discharge situations.
The accumulator isolation valve status is included in the emergency core cooling system item listed in Table 7.5-1 (sheet 5 of 11) in the FSAR. Regarding accumulator tank pressure, RCS pressure (WR) and accumulator isolation valve status provides adequate information to the plant operators for determining if the accumulator should be isolated or vented when proceeding to a cold shutdown condition and determining if the accumulator has discharged.
4.
ACCUMULATOR ISOLATION VALVE POSITION - Accumulator isolation valve status is included in the unergency core cool-ing valve status (one pair of lights per valve) item listed in Table 7.5-1 (sheet 5 of 11) in the BVPS-2 FSAR.
5.
PRESSURIZER HEATER STATUS - Four pressurizer heater banks are pe rmanent ly connect ed to the Class LE Emergency Buses. The plant computer displays total bank heater power fo r indication of energization of all heater banks.
In addition, total bus current is available at the SPDS with 0-3000 ampere range.
Each bank of heaters draws either 450 amps or 562 amps depending on the bank which is discernable to the operator to verify bank energization. The above information together with pressurizer heater breaker pos it ion status ind icat ion (see Table 7.5-1) are adequate to determine proper heater energization.
6.
QUENCH TANK TEMPERATURE - The operating staf f only utilizes quench tank conditions to discern if abnormal condi-tions exist (see BVPS-2 Emergency Operating Procedure E-0, step 31). The operator is not required to determine an exact indication of the temperature conditions in the quench tank.
A range of 350*F is adequate to determine if abnormal cond it ions exist.
In addition, the quench tank is provided with two tank rupture disks with an activa-tion pressure of 100 psi. This prevents the temperature from exceeding the upper temperature range provided.
7.
STEAM GENERATOR LEVEL - BVPS-2 has installed Model 51 steam generators.
The narrow range span on the Model 51 steam generator is 14 4 inches with the lower tap at 443 inches above the top of the tubesheet.
The wide range span on the Model 51 steam generator is approximately 576 inches with the lower tap approximately 12 inches above the top of the tubesheet.
The distance from the top of the tubesheet to the top of the swirl vane cylinde rs is 539 inches.
8.
CONTAINMENT ATMOSPHERE TEMPERATURE - Containment atmosphere t empe ratur e is not a BVPS-2 key variable and is not used in the BVPS-2 Emergency Operating Procedures for determining containment cooling. The key variables that we re chosen for monitoring the accomplishment of containment cooling are containment spray flow (Category 2), contain-ment water level (WR and NR)(Category 1), containment spray system valve status (Category 2), and containment pressure (Category 1).
Immediately af ter containment spray is init iat ed, the containment atmosphere is saturated steam and the temperature can be determined based upon containment pressure.
Since the BVPS-2 Emergency Operating Procedures do not utilize containment atmosphere t empe rature to verify con-tainment cooling, containment temperature has been classified as a Type D, Category 3, variable.
9.
CONTAINMENT SUMP WATER TEMPERATURE - Containment sump water temperature is not used fo r emergency core cooling system operation or assurance of net pos it ive suction head (NPSH) because NPSH calculations conservatively assume saturated water is present (see BVPS-2 FSAR Section 6.2.2.3.2).
Containment water level measurements indicate the amount of water in containment a nd, as described in i t em 13 (cont ainme nt atmosphere temperature), containment cooling is verified by other parameters.
In addition, qualified recirculation spray pump suct ion line t empe rature ins trumentation meet ing Reg. Guide 1.97 Category I criteria is provided and displayed in the control room with a range o f 0-200* F.
10.
RAD 10ACILVE GAS HOLDUP TANK PRESSURE - The radioactive gas holdup tank design pressure is 100 ps ig.
The ins t ru-mentation provided monitors tank pressure for normal operating conditions.
Overpressure protect ion is provided by one rupture disk per tank set fo r 100 psig.
Since the tank is protected at 100% of the design pressure and since operator act io n is not pr ed icat ed on pressures in excess of 100% design pressure, add it io nal range of pressure indication to 150% is not considered necessary.
11.
CONDENSER AIR REMOVAL SYSTEM EXHAUST - Condenser air removal sys t em exh au st ins trumentation is not required since the air ejector is routed through the BVPS-1 process vent wh ich is a cannan plant vent. Reg. Guide 1.97 requires that instrumentation with a range of 10-6 to 10 uCi/cc be installed to monitor this common plant vent.
BVPS-1 3
5 has a monitor with the range of 10-6 to 10 uCi/cc which conforms with the guidance criteria in Reg. Guide 1.97.
12.
PARTICULATES AND HALOGENS - BVPS-2 has only one final effluent pos t-ac c id e nt release po int fo r plant ve nt ilat ion systems, wh ich is the elevated release (see plant vent rad iat ion level item).
These parameters will be monitored by the elevated release effluent monitor.
\\
13.
AIRBORNE RADIOHALOCENS AND PARTICULATES - The range of the instrumentation utilized to measure this parameter is prov ided in Attachment 3 fo r the single-channel and mult i-channel analyzers.
Other information has been provided in FSAR Table 7.5-1 under Site Environmental Radiation Level.
14.
PLANT AND ENVIRONS RADIOACTIVITY - The range of the instrumentation utilized to measure this parameter is' pros ided in Attachment 3 for the mult i-channel analyzer.
The range provided meets the guidance criteria of Reg. Guide 1.97 - for this paraneter.
Other information has been provided in FSAR Table 7.5-1 under Site Environmental Radia-tion Level.
15.
PLANT AND ENVIRONS RADIATION - The range of the portable radiation monitors has been provided in the response to NRC comment No. 4 -(INEL Conclusion) in Attachments 1 and 3.
The ranges provided meet the guidance criteria of Reg. Guide 1.97 for this parameter.
Other information has been provided in FSAR Table 7.5-1 under Site Environ -
mental Radiation Level.
ATTACHMENT 3
PORTABLE SURVEY INSTRUMENTS LABORATORY INSTRUMENTS Type Meter Range Type Detection Range Minimum Detectable Activity G-M Pancake 0-50,000 CPM Single-Channel 6 digit sc ale r 8.7 x 10-10 uCi/cc (1-131) 3 (Frisker) 0-60,000 CPM Analyzer for 20 ft sample
G-M Low Range 0-200 mR/hr.
Mult i-Channel 1.6 x 10 Analyzer for 20 f t3 sample **
G-M High Range 0-20 R/hr Gas Flow 6 digit sc ale r 1.5 DPM (Sr-90, Y-90)
G-M Combination Probe: 0-200 mR/hr Proportional Internal:
0-2 R/hr Counter G-M Extendible 0-1000 R/hr Na1 (TL) 6 digit scaler 7.0 x 10-7 uCi/ml (Co-60)
G-M Po rt ab le Low Range: 0-200 mR/hr GM 6 digit sc ale r 48 DPM (Tc-99)
Mid Range: 0-200 R/hr High Range: 0-10,000 R/hr Alpha 6 digit sc ale r 1.35 DPM ( Pu-2 39 )
Scintillation Ion Chambers 0-5 R/hr l
l Ion Chambers 0-50 R/hr the uppe r limit fo r Ion Chamber 0-1.999 R/hr
- For the single-channel analyze r,5 3
2.2 x 10-uci/cc fo r a 20 ft Ext endib le 0-199.9 R/hr detect able act iv ity is 0-19,990 R/hr sample.
Ion Chamber 0-10,000 R/hr the uppe r limit fo r
- For the mult i-ch annel analyze r, 3 3
10-uCi/cc fo r a 20 ft Alpha Scintillation Count Rate Mode:
0-10,000 CPM detectable act ivity is L.0 x Scaler Mode:
6 digit sample.