ML20067B170
| ML20067B170 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 11/29/1982 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.2, TASK-2.F.1, TASK-3.D.3.3, TASK-TM SBN-390, NUDOCS 8212060075 | |
| Download: ML20067B170 (12) | |
Text
SEAB N STA M IPUBLIC SERVICE
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Companyof New Hampshire 1671 Worcester Road Framingham, Massachusetts 01701 (617) - 872 - 8100 November 29, 1982 SBN-390 T.F. B7.1.2 United States Nuclear Regulatory Connission Washington, D. C. 20555 Attention:
Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) USNRC Memorandum, dated October 14, 1982, " Notice of Meeting Regarding Open Items in the Safety Review,"
L. L. Wheeler to J. D. Kerrigan (c) USNRC Memorandum, dated September 17,1982, " Radiological Assessment Branch Site Tour of Seabrook Station,"
L. L. Wheeler to J. D. Kerrigan
Subject:
Response to Open Items (SRP 11.5.2, 12.3.2, 12.3.4; Effluent Treatment Systems Branch, Radiological Assessment Branch)
Dear Sir:
The following open items were discussed at the referenced meetings. A summary of each Open Item and our re.iponse is provided below:
1.
Open Item (SRP 11.5.2; Ef fluent Treatment Systems Branch)
Summary: The Process and Effluent Monitoring and Sampling System provision for radioiodines and particulates during the course of a postulated accident has not been addressed.
Response
In accordance with NUREG-0737 (Table II.F.1-2), provisions for obtaining samples of radioiodines and particulates from plant gaseous effluents, during the course of a postulated accident, have been included in the design of the Process and Effluent Monitoring and Sampling System.
A detailed discussion will be incorporated in OL Application Amendment 48 in FSAR Section 12.3.4 entitled " Plant Vent Monitor" as follows:
Provisions for obtaining samples of radioiodines and particulates during the course of a postulated accident are included in the Seabrook design as part of the plant vent monitor. These sampling provisions are located downstream of the isokinetic nozzles. The air flow enters the sample conditioning skid of monitor RM-6528 at a flow rate of :::: 0.06 cfm during 8212060075 821129 PDR ADOCK 05000443 PDR A
United Statco Nuclear Reguistory CommiCaicn November 29, 1982 Attention:
Mr. George W. Knighton Page 2 postulated accident conditions. This skid is intended to provide representative particulate and radioiodine samples for laboratory analysis (for normal operation as well as accident conditions) and to prevent contamination of the gas monitors. A multiple filter arrangement is provided so as to allow sampling capabilities for the duration of the measurement period. Each filter is equipped with a 4 77' solid lead shielding and quick disconnect fittings to minimize personnel exposures.
In addition, all functional control is done remotely.
2.
Open Item (SRP 11.5.2; Radiological Assessment Branch)
Summary : The applicant has not included noble gas monitors for the steam generator atmospheric relief valves or the safety valves as required by NUREG-0737.
Response
FSAR Table 11.5-1 (Sheet 1 of 2) has been revised (see Attachment A) to include the Range and Reference Isotope of the Main Steam Line Monitors. The revised version of FSAR Table 11.5-1 will be included in OL Application Amendment 48.
3.
Open Item (SRP 12.3.2; Radiological Assessment Branch)
Summary : Submit information pertaining to Item II.B.2 of NUREG-0737,
" Design Review of Plant Shielding and Environmental Qualification of Equipment for Spaces / Systems Which May be U ed in Post-Accident s
Operations."
Response: The Radiological Assessment Branch Review (Mr. Sy Block) has been provided a copy of the Seabrook Post-Accident Shielding Analysis for his review.
4.
Open Item (SRP 12.3.2; Radiological Assessment Branch)
Summary : Submit information pertaining to Item II.F.1.3 of NUREG-0737,
" Containment High-Range Radiation Monitor."
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Response
FSAR Section 12.3.4.1.b.3 (FSAR Page 12 3-16) has been revised
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(see Attachment A) to include the commitment to " design, locate, l
calibrate, and qualify" the containment high-range radiation monitors in "accordance with Table II.F.? -3 of NUREG-0737. "
5.
Open Item (SRP 1).3.2; Radiological Assessment Branch)
Summary: Submit information pertaining to Item III.D.3.3 of NUREG-0737,
" Improved Inplant Iodine Instrumentation Under Accident Conditions."
Response
A new FSAR Section 12.3.4.3 entitled " Post-Accident Inplant Iodine Assessment," will be included OL Application Amendment 48 (see Attachment A).
FSAR Section 12.5.2.1 has been revised (see Attachment A) to address gamma detection equipment which is available in the Health Physics Counting Room and Radio-Chemistry Laboratory to detect the presence of l
iodine in air samples. The revised version of FSAR Section 12.5 2 1 will be included in OL Application Amendment 48.
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a Unitcd Statas Nuclur Regulctory Commiraion Noyzaber 29, 1982,/
Attention:
Mr. George W. Knighton s
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Open Item (SRP 12.3 4; Radiological Assessment Branch),;
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Summary: Airborne radioactivity monitoring gentilation monito"rs are
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~1 installed downstream of filters so they can not monitor for inplant J'
airborne radioactivity.
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Response
FSAR Section 12.3.4.2.b.,2. tc ) (FSAR Page 12.3-20) h$s been,
'T-j revised (see Attachment A) to include monitoring of Primary Auxillary 5
Building exhaust air upstream of filt.ers.
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j, FSAR Section 12.3.4.2.b.5 (FSAR Page 12.3-231 has been revised (see
.I Attachment A) to include an increase in the number of Portable Continuous '
Air Monitors and their normal locations'.
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' a The above FSAR revisions will be incluCed in OL Application Amendment 48.
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Philip Ahrens, Esquire Assistant Actorney General Department of the Attorney General Augusta, ME 04333 1
l l-i Representative Beverly Hollingworth
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Coastal Chambcr of Commerce 209 Winnacunnet Road Hampton, NH 03842 William S. Jordan, III, Esquire Harmon & Weiss 1725 I Street, N.W.
Suite 506 Washinr, ton, DC 20006 P
E. Tupper Kinder, Esquire Assistant Attorney General Office of the Attorney General
.j 208 State House Annex Concord, NH 03301 Robert A. Backus, Esquire 116 Lowell Street P.O. Box 516 (c;
Manchester, NH 03105 t
Edward J. McDermott, Esquire Sanders and McDermott Professional Association 408 Lafayette Road Hampton, NH 03842 Jo Ann Shotuell, Esquire Assistant Attorney General Environmental Protection Bureau Department of the Attorney General One'Ashbarton Place, 19th Floor
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TABLE 11.5 !
(Sheet I af 2)
PROCESS AND U FLUENT RADM TION O NITORS (hote 5)
ALARM BACK-RANGE SET INSTRUMENT DETECTOR CRD.
LOW-HICH POlFT d2FEP1NCE DETECTOR SAFETY ENERCT* IDOP DIAC. P&lD' VAC ED. RE-DESCRIPTION TYPE
< er /h r (dCi/ec) hCt /cc )
J OTCPL QTY. PER UNIT CLASS LEVEL 9763-M 9763-F 6502 Weste Gas Inlet to Canmaa Scint 15.0 10-2 10*7 I33 4
xe 1-Unit I only Non IE Note 1 506897 805611 Carbon Delay Beds 6503
- s ete Cas compresser Canssa Scint 15.0 10'3 10*I 85 Kr 1-Unit I only Note 1 506898 805612 Inlet l
6504 H Ces Compressor Caumaa Scint 15.0 10~
10*I 2
Kr 1-Unit 1 only Note 1 506899 805612 Disch.
E 6505 condenser Air Evac Beta Scint 0.5 Note 3 Xe I per Unit Note 1 506055 202093 6500 Boron Recovery Stor.
Caussa Scint 1.0 10 10 Co
,1 I.CSI l-Unit 1 only Note 2 506105 805614 Tank Inlet 6501 Baron Recovery Test Cassaa Scint 2.5 to 10' Co
.I I CS 1-Unit I only Note 2 506113 805624 en Tank Inlet o
N 6515,6516 Primary Component Cansaa Scint 2.5 10~
10~3 tn ~
,1'
.CS 2 per Unit Note 2 506190 805016
{
Co Cooling Water 3
N 6500 Liquid Waste Test Tk Caesaa Scint 2.5 10 43
-6
-2 g,18 131 l3?
g l-Unit I only Note 2 506927 805621 Disch to CWS S
6514 Waste Liquid From Cansaa Scint 2.5 10.-6 10 c,%, gl31,c3137
-2 1-Unit I only Note 2 506931 805621 Evaporators G510,6511 Steam Cen Blowdown U
j 6512,6513 Sample Loops 1,2,3,4 Canuma Scint 2.5 10 10 j
-6
-2 58,gl31,c3137 Cc 4 per Unit Note 2 506815 805025 0519 Steam Cen Slowdown Canmaa Scint 2.5 10-10' Co 8,g!31,g3 t per Unit.
Note 2 506734 805024 137 Flash Tank Drain 4
6520-1,2 Reactor Coolant Cross Comma Scint 2.5 10~
10*3 IN i
Co
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.CS 2 per Unit Note 2 506297 805011 Activity Monitor i
6601-1, 6482-1 Main Steam Line Monitor CH 2.5
(-tuter)
(+ete+)
4 per Unit 506551 202074 cr k 64Q1-2, 6482-2
+4 g.
g 733
,-3, 44
- 1 3
6560 RS TK-79A & 8 Filter Qt
> 100 Note 4 1-Unit I only Non IE 506s s 805613 m
M (D w rr 6561 Screen Monitor CM 15 Note 4 1-Unit I only Non IE 506694 805613 e
gg 6504 Screen Monitor CB 15 Note 4 1-Unit 1 only Non IE 586692 805613 l
- See Table 11.5-4 (Sheet 2) for notes.
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A typical channel is shown in Figure 12.3-18.
High radiation during refueling at the manipulator crane area in the containment structure initiates isolation of the containment purge and vent system.
Detectors designated as non-Class lE located inside the containment structure are not designed to operate following a major LOCA, and are assumed to be not available to monitor post-LOCA conditions inside containment.
Refer to Section 11.5.2 for a discussion of the local microprocessor provisions and operating details.
1.
Area Monitor Detectors The area monitors employ Geiger-Mueller and ion chamber gamma detectors, as indicated on Table 12.3-13.
2.
Class IE Requirements Separate redundant cabinets are provided in the control room for control, recording and remote indicatioa for ti.e monitors in Table 12.3-13 designated as Class IE.
These cabinets and
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Clast IE srea monitors are powered from their respective Class IE inverters. Class IE monitors supply their data to the RDMS host computer through an IEEE-279 acceptable isola-tion device. No information er alarm setting is permitted between the RDMS host computer and the Class 1E equipment.
All set point changes and check-source insertions are performed locally or from hard-wired modules in tae control room.
3.
In-Containment High Range Monitoring Class 1E redundant detectors are located inside containment near-the-top ef the d:1 to monitor conditions during post-10 _107 R/hr. The 0
LOCA conditions. The detector range is electronics cabinet is located outside containment in til-electrical tunnels.
Indication and alarm is provided in the control room.24 /hsert 4.
Containment Manipulator Crane Area Monitor-Channels 6535 A and B Class IE redundant detectors are located on the manipulator crane.
In the event of a fuel handling accident, these monitors isolate the containment on-line and off-line purge (2-isolation valves.
Indication and alarm is provided locally and in the main control room.
k These manif ars will le. de,5igned, located, enI;brated and gual;Aed in accordance, WMb Table, H. F.1-3 of Nu REGr - 073 7.
12.3-16
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SB 1 & 2 FSAR Indication and alarm is available locally near the cleanup filter, and remotely in the main control room.
(e) Containment Enclosure Monitor - Channel 6568 This detector is located in the exhaust duct from the containment enclosure at the inlet to the cleanup filter. The detector monitors the gross activity exhausted from the containment enclosure.
Indication and alarm is available locally near the cleanup filter, and remotely in the control room.
(f) Control Room Air Intake Monitors - Channels 6506A and B, 6507A and B Four detectors are located in the east air intake structure and four detectors are located in the west air intake structure. Two detectors at each intake structure are dedicated to each unit.
These detectors, which are Class IE, monitor the control room air intake and automatically shut down, on a high radiation signal, their respective control room ventilat. ion fans and isolation datapers.
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Indication and alarm is provided 1ccally.
Indication, recording and alarm is provided in the main control room.
5.
Portable Continuous Air Monitors (CAM)
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Four por(able continu T r are availat>fe. These s air monito j'11ation dpt'ector which a beta sciXti p
devices are composed
' tors a fixed p' articulate fil er.
Downstream of the /
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f' ter is a ch coal cartridge hich can be removed for!
aboratory an ysis. The de ice also inc des a pumpi'ng C 0) system, flo rate measurin device, a
'croprocessor'and an q) interface onnection wit the RDMS hojr computer. The range q/ g
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of the y
's is 10-10 d 10-6 micrpuriespere ic W
cgnt irp4ter.
6.
Calibration and Maintenance i
l Refer to Subsection 11.5.2.6 for calibration and maintenance details.
l 12,3. 4. J Pos+ Ac.c; dent-In plant Todine_ Assesserertt-IA"'
The. capabing ef,ists b the. dekrMnaMon E "N '"*' ""dI le.n.\\s 'inplan4 under==ident condikons. This cePa.Wh' incladu the. use. er ate camp \\e.r5 vvh radioiochne, specNic_. camp \\e Ca"MdTS and the use. c# hi h resow. hen hamma spe.c b oscopy ins +rumentet. hon b sompE ana sis. L6mahn on podade. &
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sosnpung and tounWng room eq ipment 13 dt3c.ussed in Sub Me^
i2. 6.z. Tms ocunpbn3 cied ana\\ysis is dese.rWed in shkee pcesiares 12.3-23 to which chhn pers.onnel are. ff rdMed.
SB 1 & 2 l,dt w /'/ 6/h/,, j FSAR t7' 5.
Pcetable Continuous Air Monitors (CAM)
,f Eight portable continuous air monitors are available. The CAMS are equipped to monitor particulat_e.,aled6ee, and noble gas.
Iodine cartridges are removed from the CAMS for laboratory analysis (as described in 12.5.2.1).
The normal locations for the CAMS are as follows:
o 1 per Control Room o
1 per Primary Auxiliary Building o
1 per Fuel Storage Building o
1 per Containment (on the operating floor during refueling outages)
CAMS may be moved to other station locations as radiological conditions dictate.
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SB 1 & 2 FSAR 12.5.2.1 Counting Room Equipment The instrumentation in the Counting Rooms is used for determining airborne radionuclide concentrations, removable contamination, and radionuclide concentrations in liquid samples.
There are two Counting Rooms that house the fixed radiation detection equipment. The Health Physics Control Station has a Counting Room that is equipped with alpha, beta and gamma detection equipment to analyze routine air samples and contamination survey smears. The Health Physics Counting Room is supplemented by a Counting Room located in the Radio-Chemistry Laboratory when additional analysis capabilities are required. The gamma detection equipment includes two high purity intrinsic germanium detectors equipped with multichannel analyzers. This gamma detection equipment is available in the Health Physics Counting Room and Radio-Chemistry Laboratory. NUREG-0737, Item III.D.3.3 requires the capability to remove air samples (for iodine) to a low background area for analysis. This gamma detection equipment (described above), which is available in two locations, satisfies this requirement.
The equipment located in the Radio-Chemistry Laboratory Counting Room will be capable of detecting, as a minimum, alpha, beta, and gamma activity (as specified above). This Counting Room equipment is used primarily for quantitative and qualitative analysis of liquid.
Criteria for equipment selections are numerous and include accuracy, stability under various atmospheric conditions, sensitivity, and compatibility with many types of peripherals. One detector system is equipped with automatic sample changing and printout devices in order to maximize speed and ease of operation for large numbers of samples which could be expected during various phases of station operation.
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Indication and alarm is available locally and in the main control room for both units.
See Subsections 5.2.5.3.b.2, 5.2.5.5.b and 5.2.5.5.c for a further discussion of monitoring requirements.
(b) Waste Process Building Monitor - Channel 6531 The major potential release of airborne radioactivity in the waste processing buile'Ing is that associated with the gaseous waste processing system. The gas dryers, carbon delay beds and the two gas compressors are situated in their individual compartments, and these compartments are ventilated in such a way that they are at a negative pressure with respect to surrounding areas. The ducted ventilation exhaust is continuously sampled and monitored. The sample is returned to the ducted ventilation exhaust line which is directed ta the Unit 1 vent.
Both the sampling point and the return are downstream of the filters in the ventilation exhaust line outside the building.
Infor: nation from this channel is displayed and alarmed on the radiation monitoring system panel in the main control rocm of Unit I and locally.
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(c) Primary Auxiliary Building Monitor - Channel 6532 Three m.nimum ventilation areas have been defined for the primary auxiliary building:
(1) Heat exchanger, thermal regeneration demineralizer, and mixed bed demineralizer area, (2) Volume control tank area, and (3) Charging pump area.
These areas, which are potential sources of airborne activity, are maintained at a negative pressure with I
l respect to surrounding areas, and have their own ventilation exhaust ducting, filters, and fans which direct the exhaust air to the plant vent.
A continuous geh of thetwC)
I air sample is removed from the heting Ean-cr -f $gets o" %
- ' monitgred for particulate and gaseous p$b.
The. cAc is c: ' ---
activity.
T'c"O---le is r turned to the ventilation exhaust line, r;- N d~ D gE "hf the filters.
I Indication and alarm is available locally and in the main control room for both units.
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AIRBORNE RADIATION MONITORING SYSTEM PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE SEABROOK STATION - UNITS 1 & 2 INSTRUMENTATION ENGINEERING DIAGPAM FINAL SAFETY ANALYSIS REPORT
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FIGURE 1Z3-19
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