ML20050D574
| ML20050D574 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 04/08/1982 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO. |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| SBN-253, NUDOCS 8204120334 | |
| Download: ML20050D574 (49) | |
Text
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' PUBLIC SERVICE SEAMOOK STATION Engineedng Office:
I Companyof New Hampshir e 1671 Worcester Road Framinoham, Massachusetts 01701 (617) - 872 8100 W Apri l 8, 1982 O ro S 11N-25 3 g RECGmgO 3 T.F. B 7.1.2 - _ United States Nuclea r Regulatory Commission
, n um N%nrt~%[#A
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c~4y ' Washington, D. C. 20555 g g Attention: Mr. Frank J. Mi raglia , Chief D 0 Licens i ng Bra nch No. 3 Division of Licensing
References:
(a) Const ruc t ion Permit s CPPR-135 and CPPR-136, Docke t No s . 50-443 and 50 '444 (b) USNRC Le t ter, da ted Ma rch 1, 1982, " Requests for Add i t lona l Information,
- F. J. Miraglla to W. C. Ta 1Iman Su bjec t : Response to 460 Series RAIs; (Effluent Treatment Systems Branch)
Dea r S i r : We have a t tached responses to the subject RAls with the following exceptions: 460.13, 460.27, 460.36. l t Very truly yours, l YANKEE ATOMIC ELECTRIC COMPANY y J' John DeVincenti s Project Manager At t a c hment
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e e Question: RAI 460.1 (a) Based upon information presented in FSAR Section 6.5.1, the Scabrook Station does not meet Acceptance criteria II.2.c of SRP 6.5.1, Rev.1. The containment enclosure emergency air cicaning eyotes flow rate is It is the staff's not indicated in the control room nor is it alarmed. position that the flow rate abould be indicated in the control room and that alarta at high and low flows occur at the cain control board (MCB). For the fuel atorage building e=crgency air cleaning system, Section 6.5.1.5.b indicates that an alarm will occur in the MCB on a high dif ferential pressure signal but the section does not state whether there is a a p signal in the MCB or whethero p is , recorded in the MC5. In addition, the section only indicates that there is flow instrumentation and not the particular type of flow instrumentation other than Section 9.4.2 which states that an alarm in MCB will occur under off-normal flow conditions. It is our position that the MC5 include an indication of a p and flow rate and that both paraceters be recordad. Response :
- 1. Containment Enclosure Emergency Air Cleaning System The last paragraph of subsection 6.5.1.5a is being revised in the FSAR Amendment 45 to state that flow rate is indicated in the control room and high and low flow alarma are also provided in the control room.
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- 2. Fuel Storage Building Emergency Air Cleaning System The fuel storage building emergency air cleaning system has the following instrumentation:
- 1) low flow switches at fans 11 A&B discharge which is alarmed on the MCB and the cvent recorded;
- 2) high A P switch across the whole filter train which is alarmed on the MCB and the event recorded;
- 3) local A P indication across cach filter element providing auxiliary operator with filter element condition.
c l This system operates with a constant flow and the above alarns would indicate off-normal conditions due to fan probicms or filter clogging. We feel that this instrumentation provides the pertinent infornation required by Regulatory Guide 1.52. i
QUESTION 460.2 Tabic 6.5-1 of the FSAR indicates that heaters are not required for the containment enclosure emergency air cleaning system. No justification is provided as to why they are not required nor how an efficiency for methyl radioiodine of 99% was claimed without such heaters or humidity control devices. It in the staff's ponition that credit for 85% removal of methyl radioiodine will be given without some form of humidity control. ANSWER The ambient design conditions for the site are 880F dry bulb with a maximum relative humidity of 74)4%. Section 5.5 of ANSI 509-1976 states (in affect af the time of equipdent purchase) that an "approximately 70% RH" is requiped upstream of the moisture separator. Only 33% of the , total air supplied.co the containment enclosure area is outside air. The remainder is recirculated by the containsont enclosura cooling units as explained in Section 9.4.6. The cooling units will maintain the space temperature at or below 104 F at the outside dasito conditions. Therefore, since no moisture is added to the' supply air system, the relative humidity will not exceed 50%; which is less than the 70% RH required by ANSI N509. I l l I
.e RAI 460_. 3 Table 6.5-1 and 6.5-2 has indicated that the moisture separator will act as a prefilter in the containnent enclosure emergency air cleaning system filter systema. Provide justification for the exception that no prefilter is required as called for by Acceptance Criteria 11.2.a of SRP 6.5.1, Rev. 1.
Include in your justification a discussion of particulate removal efficiency in the moisture separator at times of low relative humidity or entrained moisture and an analysis of REPA filter particulate leading without a pre-filter. Since this system is used as a backup to the H2 purge, it should contain a profilter or a medium efficiency filter.
RESPONSE
Regulatory Giide 1.52, Revision 2i Section C.2, permits the use of denisters as prefilters for HEPA filters inian ESF system. The demister element consists of a 5 " chick 0.006" diameter 340 stainless steel maah and fiberous glass fill. The " dry" efficiency of thq desister 'is approximately 45% when tested in accordance with NBS Dust Spot Test. This efficiency is similar to that of a prefilter. We consider the dentater to serve a dual purpose, that of a demister and a prefilter. Therefore, there is no need to consider HEPA filter particulate lopding without a pref Liter for this application. f I l I l 1 I . r h I
QUESTION 460.4 Regulatory Position C.3.n of Reguistory Guide 1.52, Rev. 2, corresponds to Acceptance Criteria II.4.1 SRP 6.5.1, Rev.1. The applicant's response to this regulatory position, as presented in Tables 6.5-1 and 6.5-2, is confusins. Indicate whether the two ESF filter systens maat Acceptance Criteria II.4.1. ANSWER T The fuel storage building and containment enclosure air cleaning units and associated ductwork are located within the " contained space" as outlined in ANSI N509-1976, section 5.10.8.1, referenced in C.3.n of Regulatory cuida 1.52. Therefore, any leakage from the high pressure ducts will be re-filtered through the air cleaning units.
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QUP.STION 460.5 Verify that the filter bank for the ESF syster.s are 4 inches in depth. ANSVDL All ESF filter systems have 4 inch thick carbon beds. These systems are: the containment enclosure emergency exhau4t and the fuel storage building exhaust units. Each filter bed is constructed to meet the requirements of Reg. Guide 1.52 and ANSI N509. This dimension will be added to Tables 6.5-4 and 6.5-5. s e l - l l l l l
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TABLE 6.5-4 (Sheet 2 of 2) Component Parameter
- 3) Carbon Adsorber (cont'd)
Media Activated Coconut Shell Carbon Impregnating Material K13 Ignition Temperature 3400C Bulk Density 32 lbs/ft3 Hardness 953 min . Mesh size (Tyler) 8 x 16 Depth of carbon bed 4 inches l Total weight of carbon 806 lba Carbon Bed Envelope Material Type 304 Stainless Steel
- 4) Filter Mounting Frames Type 304 8tainless Steel
$) Filter System Housing Epoxy Costed Carbon Steel
- 6) Ductwork Galvealsed Steal -
1 7) Fan Carbon Steel i l r i 9
. i SB 1 & 2 (To be incor-FEAR porated in Amendment 45)
TABLE 6.5-5 (Sheet 2 of 2) Component Parameter
- 4) Carbon Adsorber Attenuation factor for elemental 99%
todine per 7" bed depth at 70% RH Attenuation factor for methyl 99% iodine per 2" bed depth at 70% RH Media Activated Coconut Shell Carbon Impr,egnating Material KI3 - Ignition Temperature 3400C Bulk Density 321 lbs/ft3 Hardness 95% min Mesh eine (Tyler) 8 x 16 .
. e Depth of carbon bed 4 inches Total weight of carbon ,
5936 lbs Carbon bed envelope material Type 304 Stainless Steel, l 5 )* Filter Mounting Frames Type 304 stainless Steel l
- 6) Filter System Housing Epoxy Coated Carbon Steel
- 7) Duc twork Calvanized Steel
- 8) Fan Carbon Steel I
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s QUESTION 460.6 Figure 9.4-2 shows one filter train of the containment enclosure emergency air cleaning system with a roughing filter and the other train with a moisture separator. khich train is correct? t ANSWER _ Both filter units of the containment enclosure emergency air cleaning system are equipped with moisture separators. Figure 9.4-2 will be corrected to reflect this. L 9 4 m e
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381&2 FSAR RAI 460.7 What is the design flow rate of the Recovery Evaporation Roboiler Pump which is sleeing from Table 9.3-87 RESPottSE The Recovery Evaporator Reboiler Pump has a design flow rate of I 12,000 gallons per minuce. -
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IAI 460.8 On pg. 9.3-66 of the FSAR, it is stated that "... dikes are provided around tanks to contain any spills." In addition to the boron waste storage tanks, identify other tanks to which this statement refers. RESPONSES Other tanks installed inside diked areas are the recovery test tanks, tha waste test tank , the unit #1 reactor makeup water storage tank, the refueling water storage tanks, and spray additive tank. For Unit 2, the refueling water and spray additive tanks are diked. O.,e . . S O be
ete. i . . . . . . . . . . , < , , - ~ . . . . . . . . SB 1 & 2 FSAR RAI 460.9 What type of bed is the recovery demineraliser; cation, anion, mixed? RESPONS(* The recovery desineralisers are mixed bed. I ~s 9 e l l $'~ .. l? O
l 551&2 F8AR RAI 460.10 Figure 10.4-1 of the FSAR does not show where the liquid from the mechanical vacuum pumps goes and whether it is treated as a radioactive liquid. Please l indicate how this liquid is collected, how its is processed, if at all, and ) whether it is discharged. i RESPON8E: Entrained liquid and condensate from the condenser air removal lines is collected in the moisture separator on the vacuum pump skid. An overflow line, with internal float valve, discharges this liquid to the turbine building drainage system. The liquid is considered non-radioscieve, consistant with the balance of the air removal system. a e S i. , I ' . ) e-e e
SB 1 & 2 FSAR RAI 460.11 The main condenser evacuation system has not been designated as a non-nuclear safety (NNS) system in Table 3.2-2 of the FSAR, nor in Section 10.4.2. The components of this system should be designed to your NNS quality group to meet the requirements of Acceptance Criteria II.2 of SRP 10.4.2.
RESPONSE
The main condenser evacuation system is a non-nuclear safety (NN8) system. The vacuus pumps are designed to manufacturers standards. Piping and valves are designed to ANSI 331.1 (see revised 75AR Table 3.2-2). O tuem 9 E D I s i i (.
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ABS Principal Bafety Design /Const. Code Seismic FSAR Codes /Stds.__ Class Category Building (Il} Supplier Notes Systems and Components Class _. Section , I PC/EF AE 3 ASME.III 3 To Emergency.Teedwater Pomp Turbisd
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.- TB MIts ANSI 331.1 -
Other >
' p 10.4.2 Main Coodenser Evacuation System , ,
- - TB AE Vacuum Pasp IEIS MFRS. STDS. AE
- T5 Piping and Yalves IRES ANSI B31.1 -
t 10.4.3 Turbine Cland Sealing System . m Cland Steam Condenser and TB AE m" Mars MFRS. STDS. Erk- star Fana - T8 AE in - NES MrRS. STDS. - Piping and Yalves N e. u 10.4.7 Coedensate and feedwater System
- - T3 AE NES MFES. STDS. ,
Condenaato Fump '
- - T3 AE Heetar Drain Pump ERS IIFRS. STDS.
- - 75 AE IRIS MFES. STDS.
Steam Cenarator Feed Pump
- - TB AE MS MFRS. STDS.
- Steam' Censrator Startup Feed Puimp'
- - TB AE MIIS ASME VIII ,
Feedwater . Beater yv Q Piping and. Valves 2 I PC/CS AE ES" 2 ASE III S. 5 E From Fifat Isolation Valva I S. ~
- Outside:Containesat to . S .R Steam d aerator s. 8 %
, - TR AE u a ANSI B31.1 NNS V Other-l e
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SB 1 & 2 FSAR RAI 460.12 The turbine gland sealing system has not been designated as a NNS of The components system this in Table 3.2-2 of the FSAR, nor in section 10.4.3. system should be designed to your NNS quality group to meet the Acceptance Criteria of SRP 10.4.3.
RESPONSE
The The turbine gland sealing system is a non-nuclear safety (NNS) system. gland steam condenser, exhauster fans, piping and valves are danignated to manufacturers standards (see revised FSAR Table 3.2-2).
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SB 1 & 2 TSAR RAI 460.14 From Figure 10.4-7, Sheet 1, it appears that distillate from the distillace cooler will be discharged to both the vaste test tank and to the main condenser. Should valve SB-V208 be shown normally closed in this figure?
RESPONSE
Distillate will normally be discharged to the main condenser, therefore valve SB-V209 should be shown as normally closed. h l e h 9 ,. 9,* l I
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RAI 460,15 Table 9.3-3 indicates that the leakage rate in the fuel storage butidtng in 20 gym. Is this correct or should it be 20 gpd7
RESPONSE
Table 9.3-3. Sheet 1 of 2, has been modified to provide clarification. ! ~ I- ~; b t , [ . _ _ . . . _ _ [ 2 g
SB1&2 i (to be incorporated in Amend. 45)
- TABLE 9.3-1 (Sheet 1 of 2)
PLANT LEAKAGE SOURCES s
- a. Containment
- 1. Sump A Source Normal Leak Rate RC Pump 1A, #3 Saal 3.5 spd RC Pump 1B, #3 Seal 3.5 gpd RC Pump 10, f3 Saal 3.5 spd RC Pump 1D, #3 Seal 3.5 spd ;>
Six Containment Cooler Drains Negligible
- 2. RCDT RC Pump 1A, #2 Seal 3.0 gph RC Pump 13, #2 Seal 3.0 gph RC Pump 1C, #2 Seal 3.0 gph -
RC Pump ID, #2 Seal 3.0 gph
- b. primary Auxiliary _8ui] ding Sample Sink 100 spd conLulasvut. r.uclu== = coulic.a Units (2) 1 gph, anah
- c. RI1R/CBS Equitzsent Vaults to Sumps A and B ,
i All Sources Negligible
- d. Fuel Storate Buildina Spent Fuel Cask Washdown
- 20 spa l
- e. Wasta Processing Buildina Sample Sink (Elev. ,(-)3 '-0") -- 100 spd
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85 1 & 2 FSAR RAI 460.16 Provide justification for taking exception to Regulatory CuiEe 1.143 by designing the chemical drain tank and the chemical treatment tanks to Standard Ps-15-49. Eg8PONSEt No exception to Reg. Guide 1.143 has been taken. These tanks are collection points for waste prior to treatment by the liquid waste system and are specifically excluded from the requirements of Reg. Guide 1.143 by Section 3 of this Reg. Guide. S
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. - SB1&2 FSAR RAI 460.17 Provide for the components the volume or flow rates, as appropriate, to the piece of equipment and the number per unit.
a) chemical drain tank b) chemical drain transfer pump e) chemical drain treatment pump d) chemical drain treatment tank e) reactor coolant drain tank (RCDT) i f) RCDT pump g) RCDT heat exchanger
RESPONSE
Volumes, flow rates and number per unit are tabulated belows Name Volume / flow rate Number / unit s Chemical. drain tank 1000 gallons ,,,, 1* a Chemical drain transf,er pump 40 spa 1* Chemical drain treatment pump 30 gpm 2* Chemical drain'creatment tank 3600 gallons 2* Reactor coolant drain tank 350 gallons 1 RCDT pump 100 gpm 2 RCDT heat exchanger 100 gym 1
- Indicates common to both units. _
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FSAR RAI 460.18 Which demineralisers are considered regenerable and where does the regenerate solution go?
RESPONSE
The only domineralizers that are regenerated are the steam generator blowdown recovery domineralisers and the makeup water treatment system domineralizers. All regenerate solution are neutralised and discharged to the circulating water system. l l l l l l l
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- SB 1 & 2 FSAR RAI 460.19 Figure 11.3-1 does not appear to show a flow path from the H2 compressors to the H2 surge tank. Please provide a drawing which indicates this flow path.
RESPONSE: I A line between the H2 surge tank and the 150 psig header is used for both . i charging and discharging the surge tank. An additional arrow is shown on the revised Figura 11.3-1, sheet 2. e f 4 N e
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- 83162 rsu j RAI 460.20 Will the iodine guard bed of the RGWS be tested to the requirements of Regulatory cuide 1.1407 RESPONSgt tio ;
the function of the iodine guard bed is not within the scope of Regulatory Guide 1.140. .
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. RAI 460.21 Discuss the impace upon the operation of the RGWS if the purge gas condenser is inoperable.
RESPONSE
The RGWS is designed with three waste gas dryers. One of them is in operation, the second is in regeneration, and the third is on standby and ready for operation. Therefore, in case the purge gas condenser is inoperable, the regeneration loop will be shut off; 96 hours (on-strema time of the standby dryer) will be enough time for any maintenance work on the condenser.
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f i QUESTION 460.24 Figure 9.4-4, Sheet 1, does not include parameters to be monitored and alarmed in the filter train. Please include them. ANSWER instrument-Figure 9.4-4, Sheet 1 is being revised to indicate filter unit ation as required. l
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QUESUO.9 460.25 Sections 9.4.12.2.b.3 and 9.4.12.2.c.3 indicate that the exhaust f rom the administration and acrvice building (RCA) is directed thro, ugh an absolute filter and a radiation monitor. A drawing showing the location of the filter and the monitor was not found in Section 9.4,11.3, or 11.5 of the FSAR. Please indicate where a figure containing such inforcation may be found in the FSAR or provide one if one is not in the FSAR. What parameters of the filter system are monitored and alarmed? This monitor should be included in the discussion presented in Section 11.5.
RESPONSE
The exhaust from the administration and service building (RCA) does have This monitor, its function, and a radiation monitor associated with it. locations are described in Subsection 12.3.4. Indicating differ-A new Figure 9.4-15 will be provided in Amendment 45. ential pre'esure switches are provided for each filter section, HEPA and pre-filter. .The differential pressure across each filter section is alarmed at: a local control panel (CP-54) and at the computer. oo.. a.
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460.26 Does a high pressure in the exhaust from the PAB clean-up exhaust fans result in an alarm on the FCB7 RESPONSE: These is no high pressure alarm monitoring the discharge of the PAB normal clean-up exhaust fan. 4 1
SB 1 & 2 FSAR RAI 460.27 Section 11.3.2.2 states that some cubicles of the RGWS will be continuously monitored for H2 and that in the event of high H2 concentration: a) the affected. components of the process stream will be isolated and/or the affected component purged with N 21 b) the affected cubicle will be ventilated to reduce the H2 concentrationg and c) unnecessary personnel will be evacuated from the area. It appears that the ventilatica to reduce H2 concentration could result in the sddition of air in the ventilation systems in the ambient carbon delay bed and the hydrogen surge tank area, thus resulting in a potentially explosive mixture. Another potential source of 02 could be the air conditioning units. Provide an analysis to show that the addition of air in these cubicles ~of the RGWS would not result in a deflagration or an explosive. RZSPONSE: The lowest explosive level of El in air is 4%. The H2 analyzer will be set to alern at less then 4% (say 3%), and the effected cubicle / equipment will be isolated. Following isolation,-the cubicle and equipment will be
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SB1&2 FSAR RAI 460.28 Our review of RGWB P& ids concludes that there are no rupture discs in the system. Please verify thIs. If there are rupture dlees then liquid seals should be provided downstrees of the discs and the design of the system should include measures to prevent the permanent loss of the liquld seals in
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RESPONSE
No rupture discs are used in the ROW system. 9 6 4 A N
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i S51&2 FSAR RAI 460.29 appears that the critical location in Based upon our review of the RGWS itis the hydrogenated vent header which is the the system for monitoring 02 source of input to the RCWS. Therefore, it would appear that one of the 02 The analysers should be analysing the influent upstream of the gas chiller. other analyser should be sequentially monitoring the inputs from such streams as the reactor coolant drain tank, PDT, letdown desassifiers, CVCT, etc. The rational for placing the 02 monitor af ter the dryer should be presented. RESPONSES In the latest revision of the RGW system, we have excluded the 02 monitor 2 in line after the dryers, and installed it as redundant to the existing 0 monitor in the upstrema line of the gas chillers. Monitortug of trace oxygen at each branch streams, such as reactor coolant drain tank, PDT, CVCT and letdown degassifier is not necessary, since all these lines are ultimately headed to a main stream atThe theanalysers inlet of the are chillers where the trace 02 analysers are installed. installed in parallel. One is in service and the other is in standby. Analyser duty rotation is administratively controlled. 9
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Sn1&2 FSAR RAI 460.30 The SER, at the construction permit stage, indicated that the RGWS was to be designed to withstand a H2 explosion. The FSAR does not indicate that the If this is a design system is designed to withstand such an explosion. change from the CP stage, provide justification.
RESPONSE
The RGWS .is designed to withstand a H2 explosion, as stated in the revised Section 11.3.1 of the FSAR. e ). 4 0 e e e
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1 11.3 RADY$hh!VICASE008WASTESYSTEM l 11.3.1 Desian Basis, Rydrogensted fission produce gases from the reactor coolant letdown stream and i f' rom the liquide collected in the primary drain tank and the reactor coolant The - drain tank are processed in the Radioactive Gaseous Weste System (BGWS). RCWS is shared by Units 1 and 2. An iodine guard bed sad a molecular sieve dryer reduce the contamination level of the gases before further processing by The carbon delay beds provide a minissam of 60 days , the carbon delay beds. Low activity aerated gas streams from xenon delay and 85 hours Krypton delay (.Section 9.3.6), and condenser vacuum the reactor pump units (plant aerated vent headersection 10.4.2) are filtered, monitored plant unit vent. The RGWS is designed to provide suf ficient processing such that gaseous
' effluents are discharged to the environment at concentrations below the regulatory limits of 10 CFR 20 and within the "as low as is reasonably achievable" guidelines set forth in 10 CFR 50, Appendix I, (see sections 11.3.3 and 11.5). The acWs also provides sufficient holdup and control of gaseous releases, as specified in 10 CFR 50, Appendix A, General Design Criterion 60. ne RGW8 can process a maximum surge flow of 1.2 scfm fram the degasifiers, which is based on the maximum letdown flow of 120.gpa from the reactor coolant system to the chemical and volume controLsystem for. each unit;. .
nis represents the most limiting plant , operating condition for the ECWS.
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' Safety Class 3, seismic Category I' components are provided in delay beds. , The portion of the waste processing building which houses the BGWS is also seismic Category 1. The quality control requirements of Section III of the ASME Boller and Pres'sure vessel Code apply to all Safety class 3 components. ne particulate filters, hydrogen gas cospressors, and hydrogen. surge . tank are designated non-nuclear safety class'. The dryer package regeneration subeystem consisting of a regeneration compressor, an electric heater, a purge gas condenser, and associated piping up to the first isolation valves is also non-nuclear safety class. The design pressure of the Safety Class 3 portions of the system is 350 peig. Redundant Table 11.3-1 liste RGWs componente and.their design parameters. components reliability. are provided to minimise operator exposure and enhance -
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Rydrogen concentration is monitored in cabieles containing Raus components to detect a leak in the system. Section 13 7.1 discusses 3048 leak or faildre. Dual oxygen monitors areAn provided in the process strema to prevent alats is initiated at a predetermined
! formation of explosive mixtures. h e RGW5 is setpoint prior to reaching a potentially explosive misture.A radiation monitor is provided
' designed to withstand a H2 explosion. line to the plant unit vent to detect an excessive release of rediati . the environment. , a' i
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i I RAI 460.31 { Table 11.4-3 of the FSAR provides the volume of solid wastes anticipated from the Seabrook Station. The volume of evaporator bottoms and other liquid wastes appears to be extremely low based upon the anticipated ' ] flow rates to the BRS, SGB, and liquid waste evaporators, and when com-pared to the solid radwaste shipped from operating PWRs. The volume of { l compactable waste is also low. Picase provide the bases for your volumes 1 of evaporator bottoms and other liquid waste, compactabic waste, and non-compactable waste. ! Response: , The annual volume of anticipated solid waste in Table 11.4-3 were esti-l l mated based on the operational data for domestic PWRs(l) which was used j in the original design of existing urea formaldehyde (UF) system. The data base used for the original solid waste management design related ' total annual solid waste shipped offsite for disposal to thermal power i output in NWhr(t). ' However, it has been recognized that since the time of the original design at the PSAR stage additional operating history on vaste generation rates for large PWRs has become available, and that this information indicates l' that the annual waste generation rates for wet wastes (spent resins and evaporator bottoms) and dry active waste are considerably larger than 2 originally expected. I Because of the current need to change our process design to replace the ) original UF solidification system, a revised equipment specification has ) been prepared and issued for the purpose of sizing and evaluating poten-tial new solid waste management systems. The design operating waste l volumes by which a new volume reduction / solidification system is to be
! sized has affectly increased the spent resin and evaporator bottom quan-t tities in Table 11.4-3 by a factor of three, and dry active waste by a factor of six, as shown below:
l spent resin: 4290 ft 3/ year evaporator bottoms and other
- liquid waste (G 12 w/o solids concentration): 11937 f t3/ year dry active waste (compacted): 29160 ft 3/ year If these resin and evaporator waste volumes were assumed to be solidified using current standard process methods in cement, with no additional volume reduction techniques applied, the final shipping waste volumes ^for wet waste would be approximately 1.5 times larger overall, or about 3 24,300 f t3 / year for both reactors combined, or equivalently 12,200 f t / year per unit. This is considered consistent with the current 3(1981) ETSB annual average PWR wet waste generation rate of 14,000 ft / year for a 3400 MWt plant, and 12,000 f t / year for dry active waste per unit.
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In addition to these design operating generation rates, the revised solid waste management specification requires that any new inplant system be able to process the design wet waste volumes in less than 1664 hours per year (within a 19% operating capacity factor). This design criteria will provide sufficient process capabilities to handle anticipated operational occurrences which could produce larger than expected waste volumes. The final waste shipping volumes are dependent on the method of solid waste processing (volume reduction and solidification equipment) which is selected to replace the original design. Table 11.4-3 will be up-dated to reflect the revised waste generation rates and final shipping volumes / curie content when that selection is finalized. ) Reference (1) Kibbey, A. 11. and Godbec , 11. W. , "A Critical Review of Solid Radioactive Waste Practices at Nuclear Power Plants", ORNL-4924, March 1974. RAI 460.32 Does the solid waste system meet the provisions of Branch Technical Position (BTP) ETSB 11-37
Response
A replacement solidification system design for the original urea formaldehyde system has not yet been selected. The appropriate system design and operating provisions of Branch Technical Position ETSB 11-3 (Rev. 2 - July, 1981) will be included in the new solid waste system design when it is selected. s 6
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I f 1 i i RAI 460. 33 i 4 Provide a description of the solidification system / process to be used j at Seabrook showing its conformance with the acceptaace criteria of j SRP 11.4. i
Response
The original radwaste solidification system design, as described in the 1 PSAR, used urea formaldehyde (UF) as a binding agent. Because recent ! industry operating experience has shown that waste solidified in UF can not be guaranteed to meet waste form criteria on free standing liquid, the existing UF system design will be replaced with a system than can insure that all appropriate requirements concerning waste form can be met. i As indicated in response to RAI 460.1, PSNH is presently evaluating the solid waste management systems commercially available, including the 4 option to employ a contract (mobile) system in lieu of a permanent system at the time of plant startup. Once a system (or mobile contract service) is selected, a full descrip-1 tion of the solidification system / process which indicates its conform-j ance with the acceptance criteria of SRP 11.4 will be provided. 1-r ! l l l
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Que cion 460.34 (11.5)_ In Section 11.5.2.3 of the FSAR. reference is made to the vent stack monitor yet no monitor is mentioned in section 11.5. Please clarify whether there is a plant vent monitor. The vent stack is the final release point for various ef fluent streams, including the PAB and the fuel storage building. It is the staff's position that there must be a continuous radiation monitor located in the plant vent. Response (Question _460.34) The Seabrook design does include a plant vent monitor. This monitor is described in Subsection 12.3.4 ,
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Question 460.35 (11.5) . Acceptance Criteria 11.C.l.a states that the gaseous and liquid pro-cess streams or ef fluvnt release points should be monitored and na= pled according to Tables 1 and 2 of SRP 11.5. Information provided in Section 11.5 of the FSAR indicates that the Seabrook Station does not meet this criteria in the following areas: a) Plant vent does not contain a continuous radiation monitor for noble gas effluents. (see question above) b) Containment purge lines do not contain a process monitor nor the capability to isolate the purge line on a high radiation monitor. (Note: Area mcnitors are not an effect,ive means for meeting 10 CFR Part 20 unrestricted area airborne con-centration limits.) c) The fuel storage building does not contain a process monitor from it exhaust to the plant vent. d) The turbine gland steam condenser exhaust is discharged to the atmosphere unmonitored. e) The turbine building sumps are to releas*e their contents on a batch basis vitti"only a sample taken and analyzed prior to release. Since there is no means to isolate the sump and since the re. lease is not monitored. a monitor la required for turbine building effluent along with.an. automatic. control feature to.is,olate the discharge.-- -
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f) A gross radioactivity monitor is required for the service water effluent line. , 9 g) The capability to obtairra grab sample in ihe stre_am from the following' sources has not been provided: (1) containment purge (2) PAB ventilation system f I (3) fuel storage building (4) waste processing building area handling radwaste (S) turbine gland steam, condenser (6) evaporator vent system ,(i.e., distillate coolers) h
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Response (Question 460.35) a) The plant vent monitor is described in subsection 12.3.4. b) The capability to monitor the containment purge lines and to isolate these lines on a high radiation indication will be included in the plant design. c) The capability to monitor the exhaust from the fuel storage building is included in the plant design. This monitoring capability is described in subsection 12.3.4. d) The exhaust from the turbine gland steam condenser will either be monitored separately, or directed to the main plant vent. c) The capability to monitor the effluent from the turbine building sumps will be included in the plant design. f) We are evaluating the possibic sources of radioactive contamination of the service water system to ensure that they are monitored. We will inform the NRC regarding the results of our review later. g) The capability to obtain grab sampics from the nine process and/or effluent streams indicated is either in the present system or will be included.
Question 460.37 Does the process and ef fluent monitoring system have the capability to replace or decontaminate on-line monitors without opening the pro-cess system or losing the capability to isolate the effluent stream? Response (Question 460.37) The capability to replace or decontesinate on-line monitors without opening the process system or losing the capability to isolate the effluent stream is included in the Seabrook design. e g . _ x 4 soa 44 g.
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,. Question 460.38 Review of the FSAR provides no information with respect to the col-1ection of radioactive wastes in the turbine building and their disposal. On page 11.2-7 of the FSAR, it is indicated that the turbine building sump will collect radioactive wastes in this building.
Table 11.5-3 of the FSAR implies that a esmple will be taken of this sump and that the sump will be released on a batch basis. From Table 11.5-2 of the FSAR, _it-can be inferred that _there la no monitor I on the discharg'e from the sump.
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Provide the appropriate P& ids which show the various' flow inputs to the turbine building sump. It is the staff's position that unless a turbine building sump can be isolated such that no flow is allowed into the sump after a sample is taken, then this discharge point requires a radiatipn monitor and in addition an automatic control feature which isolaten the discharge on a high radiation signal. Response (Question 460.38) The primary discharges into the turbine building sump is from equipment leakage which can be expected to be small. The capability to monitor the discharges from the . turbine building sumps will be installed in the Seabrook design with the appropriate automatic control features.
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Response (Question 460.39) Radiation monitor RE-6503 is correctly labeled as monitoring the flaste Gas Compressor inlet. The lines on which this monitor is located is the flow path between the char mal delay beds, and the waste gas compressor (see Figure 11.3-1 sheets 1 and 2) Question 460.39 It would appear that radiation monitor RE-6503 has been labeled incorrectly in Table 11.5-1 based upon Figure 11.3-1 sheet 2. The title would be discharged from carbon delay beds. Please verify this. L p - .. u,
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..0 460.40 llow does one tell from the Seabrook P& ids whether a monitor alarms locally or in the control room or in both locations? This also applies - to the location of indications for pressures, flow rates, radiation levels, etc.
RESPONSE: The location of alarm indications is shown in Figure 11.5-1. Monitors alarm locally, with selected monitors lighting indicator lights in the control rocos. All alarm nessages, and indications of pressures, flow rates, radiation icvels, etc. are indicated on the RDMS display / control consoles located in each control room, the health physics control point, each technical support center, and the emergency operations facility. The location of alarms and indications for process instrumentation that are not inputs to the RDMs are shown on the control loop diagrams (9763-M-506XXX and -507XXX series) . i 3 *
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