ML20065A793

Forwards Responses to Containment Sys Branch Open Item SRP 6.2.8,per TMI Action Items II.E.4.2 & II.F.1.2.Responses Will Be Incorporated in OL Application,Amend 49

ML20065A793
Person / Time
Site:	Seabrook
Issue date:	02/17/1983
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.E.4.2, TASK-2.F.1, TASK-TM SBN-470, NUDOCS 8302220166
Download: ML20065A793 (8)

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IPUBLIC SERVICE Companyof NewHamph 1671 Worcester Road Framinohom. Massachusetts 01701 (617)- 872 8100 February 17, 1983 SBN-470 T.F.B 7.1.2 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. George W. Knighton, Chief Licensing Branch 3 Division of Licensing

Reference:

(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos.

50-443 and 50-444

Subject:

Open Item Response (SRP 6.2.8; Containment Systems Branch)

Dear Sir:

We have enclosed responses to the following open items:

NRC Branch SRP Section Comments CSB 6.2.8 Containment Isolation Dependability; Containment Isolation Setpoint Essential /Non-Essential Penetrations TMI Item II.E.4.2 (Revised)

CSB 6.2.8 Containment Water Level; TMI Item II.F.1.2 (Revised)

The enclosed responses will be incorporated in OL Application Amendment 49.

Very truly yours YANKEE ATOMIC ELECTRIC COMPANY

(

John DeVincentis Project Manager l

JDeV/smh cc: Atomic Safety and Licensing Board Service List 8302220166 930217 '

PDR A

ADOCK 05000443 PDR I

i ASLB SERVICE LIST Philip Ahrens, Esquire Assistant Attorney General Department of the Attorney General Augusta, ME 04333 Representative Beverly Hollingworth Coastal Chamber of Commerce 209 Winnacunnet Road Hampton, NH 03842 Williaa S. Jordan, III, Esquire Harmon & Weiss 1725 I Street, N.W.

Suite 506 Washington, DC 20006 E. Tupper Kinder, Esquire Assistant Attorney General Office of the Attorney General 208 State House Annex Concord, NH 03301 Robert A. Backus, Esquire 116 Lowell Street P.O. Box 516 l

Manchester, NH 03105 Edward J. McDermott, Esquire Sanders and McDermott Professional Association 408 Lafayette Road Hampton, NH 03842 i i

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Jo Ann Shotwell, Esquire Assistant Attorney General Environmental Protection Bureau Department of the Attorney General One Ashburton Place, 19th Floor Boston, MA 02108 I

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6.2.8 TMI Action Plan Requirements II.E.4.2 We have reduced the setpoint for containment isolation Phase A (Hi 1) from 5 psig (the value in the Standard Technical Specifications) to 4.3 psig, the minimum practical. The setpoint was calculated as follows:

Maximum expected containment pressure during normal operation, Note 1 1.5 psig

+ Margin between maximum expected pressure and the minimum setpoint. Note 2 1.0 psig

+ Channel statistical allow-nce.

Note 3 1.8 psig

= Nominal Setpoint 4.3 psig Note 1 The maximum expected pressure is obtained from the Service Environment Chart (FSAR Figure 3.11 (B)-1). The Seabrook value is slightly higher than the maximum pressure at other PWRs since the Seabrook containment will be normally pressurized to about 0.5 psig and a continuous ru tegrated Leak Rate Test (ILRT) performed to provide early detection of problems with containment integrity.

Note 2 From NUREG 0737 Item II.E.4.2, Clarification 6.

Note 3 From the Protection System Setpoint Study Instrument span 60 psig X Channel statistical allowance (%) X3%

= Channel statistical allowance (psig) 1.8 psig

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BACKGROUND The subject table provides additional information responding to NUREG-0737 clarification of TMI Action Plan Requirements,Section II .E.4.2. The table indentifies essential / nonessential systems penetrating Seabrook Plant Unit 1 l containment and a selection basis for the essential systems. The purpose of

! this table is to address the containment isolation dependability.

DEFINITIONS l

1) Essential - Systems penetrating the containment which are necessary to mitigate the consequences of an accident.

2) Nonessential - Systems penetrating the containment which provide

! auxiliary service functions for operation of the plant, and are not l required for mitigation of accidents.

Pene- Essential System Selection Basis tration (E)

No ne ssential (NE) t X-1 E Main Steam - SG E 11A Decay Heat Removal l

X-2 E Main Steam - SG E llB Decay Heat Removal X-3 E Main Steam - SG E 11C Decay Heat Removal X-4 E Main Steam - SG E llD Decay IIcat Removal X-5 E Feedwater - SG E 11A Decay Heat Removal X-6 E Feedwater - SG E llB Decay lleat Removal i X-7 E Feedwater - SG E 11C Decay Heat Removal X-8 E Feedwater - SG E 11D Decay Heat Removal i X-9 NE RHR Pump Suction - HL #1 - --

X-10 NE RHR Pump Suction - HL #4 X-11 E RHR To Safety Injection Low Pressure Injection  !

X-12 E RHR To Safety Injection Low Pressure Injection l

X-13 E RHR To Safety Injection Hot Leg Injection 1

X-14 E Containment Bldg. Spray Containme nt Spray l X-15 E Containment Bldg. Spray Co ntainme nt Spray X-16 NE Containment On-Line Purge X-17 NE ilydrogenated Vent Hdr.

X-18 NE Containment 32-Line Purge ,

X-19 NE Spa re

X-20 NE* Primary Component Cooling De sira ble for Some Water Accidents; Isolate on 511-2 Containment Pressure X-21 NE* _ Primary Component Cooling Desirable for Some Water Accidents; Isolate on ilt-2

l. Containment Pressure X-22 NE* Primary Component Cooling Desirable f or Some Water Accidents; Isolate on Hi-2 Containment Pressure l j X-23 NE* Primary Component Cooli ng Desirable for Some l Water Acc ide nt s; Iso la t e on 111-2 l Containment Pressure l l X-24 E SI From Boron Injection Tk. liigh Pressure SI i l and Charging Pumps l X-25 E SI, High flead Medium Pressure SI t

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t Pene- Essential System Selection Basis tration (E)

Nonessential (NE).

X-26 E S1, High Head Medium Pressure SI X-27 E SI, High Head Medium Pressure SI X-28 _ NE ,. _ Seal Water to RC Pump 1A _._ _ ,_ _

X-29 NE Seal Water to RC Pump 1B X-30 NE Seal Water To RC Pump IC X-31 NE Seal Water to RC Pump 1D X-32 NE RC PRN TK To Primary DRN TK X-33 NE Chemical and Volume Control X-34 NE Floor Equipment Drain X-35 NE* RCS Sampling Required for Post-Accident Sampling Manual Bypass Operation X-35 NE SI Test X-36 NE Demineralized Water X-36 NE Nitrogen Gas X-36 NE Reactor Makeup Water X-37 NE Letdown HY X-37 NE RCP Seal Water Return X-38 NE* Combustion Gas Control May Be Required for Purging Following Some Accident-Manual Operation X-38 NE Fire Protection X-39 NE Refueling Cavity Purification X-40 NE Nitrogen to PRT X-40 NE PRT Gas Sample X-41 NE Spare X-42 NE Spare X-43 E Press. Protection Containment Monitoring Containme nt X-44 NE Spare X-4 5 NE Spare X-46 NE Spare ~

X-47 E ' Press. Protection Containment Monitoring X-48 NE Spare X-4 9 NE Spare X-50 E Press. Protection Containment Monitoring X-51 NE Spare X-52 E Containment Air Sample Containment Monitoring X-53-56 (Numbers Not Used) '~'

E '~~~~~ Press. Protection

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X-57 ~ ~

Containment Monitoring X-57 NE* Post-Accident Sampling Required for Post-Accident Sampling Using Manual Bypass X-58 NE Spare

._ __ _ X-59 NE __ ___ _ S pa re ..__ . _ _ _ _ _ _ _ . _ . . _.

X-60 E Containment Recire. Sump Co ntainme nt Spray and SI CBSTK-10B Recirculation X-61 E Containment Recirc. Sump Co nta i nme nt Spray and SI CBSTK-10A Recirculation X-62 NE Fuel Transfer Tube

5 Pene- Essential System Selection Basis tration (E)

Nonessential (NE)

X-6 3 NE Steam Generator Blowdown EllA X-64 NE Steam Generator Blowdown EllB X-6 5 NE Steam Generator Blowdown EllC X-66 NE Steam Generator Blowdown EllD X-67 NE Service Air X-68 NE Spare X-69 NE Spare X-7 0 NE Spare X-71 NE* Combustible Gas Control Required for H2 Post-Accident Sampling X-71 NE Component Cooling Water X-72 NE* Combustible Gas Control Required for H2 Post-Accident Sampling X-72 NE Component Cooling Water HVAC-1 NE Containment Air Purge Supply HVAC-2 NE Containment Air Purge Exhaust Although these systems are nonessential, they are valuable in accident monitoring and control 9

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b. Containment Water 1. eve l Instrumenta tion

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I The Seabrook design for containment water level complies with O L o

this requirement. Refer to clarification 3. for a discussion

%n -43 e of the narrow range qualification.

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oRO hk g b3 4. This requirement is not applicable to Seabrook.

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'R '- 0 5. The f,5% accuracy of the wide range level monitors provided in

$* N k FSAR Table 7.5-1 is adequate for the intended func t ion. Justi-3$d fication is provided as follows:

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'*-> a. The accuracy results in a uater capacity uncertainty of q

go'NW-a. approximacely 27,000 gallons. ._ .

W CNQ b. The capacity of the RWST (between the Tech Spec limit

• k ';6 and the Recire. Setpoint) is in excess of 325,000 gallons.

h% of this capacity, approximately 127,000 gallons would g o ,Et fill open cavities below (-)26 elevation, leaving a minimum

r Itf Q , capacity of 198,000 gallons above the (-)26 elevation Q only considering the RWST capacity.

c. In light o f b. , the uncertainty of a. will become negli-gible well be fore the recirculation phase is entered.

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Insert A The narrow range water level monitors are not required to operate after their respective sumps have been flooded as their function is to monitor operational leakage. They will only be exposed to a mild environment as any leakage that would cause a harsh environ-ment would flood their sumps and would be detectable by the wide range (recirculation) sump level-indicators and instruments moni-toring the' containment atmosphere.

The narrow range containment sump level instrumentation will be covered by the maintenance / surveillance for equipment that is located in a mild environment. This ongoing verification'of the ability of the equipment to operate in the required environmental conditions meets the requirements of IEEE 323-1974 as endorsed by Regulatory Guide 1.89, Rev. O as interpreted by the Standard Review Plan, NUREG 0800, p. 3.11-5.

The narrow range level instruments will be operable after an operating basis earthquake (OBE) as recommended by Regulatory Guide 1.45.

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