ML20198A158

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Forwards Input of Partial SER Open Item Associated w/AP600 TS on Main Control Room Habitability.Input Was Provided w/mark-up of W TS 3.7.6
ML20198A158
Person / Time
Site: 05200003
Issue date: 12/17/1997
From: Huffman W
NRC (Affiliation Not Assigned)
To: Liparulo N
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9801050300
Download: ML20198A158 (14)
v • d • e


Text

- .

Deceraber 17, 1997

. Mr. Nicholas J. Liparulo, Manager - l Neclear Safety and Regulatory Analysis

[. # -

Nuclear and Advanced Technology Division Westinghouse Electric Corporation 3i ' '

i P.O. Box 355 - .,

e Pittsburgh, PA 15230 {,

SUBJECT:

SAFETY EVALUATION REPORT (SER) O?EN ITEM ASSOCIATED WITH AP600 y,

  • TECHNICAL SPECIFICATION (TS) ON MAIN CONTROL ROOM HABITADILITY3

/ ,

,. /

/ ,

Dear Mr; Liparulo:

, l' > a l' [" The U.S. Nuclear Regulatory Commission Standardization Project Directorate has ree Ned

" ' ~ '

. 1 partial SER submittal from the Plant Systems Branch on the AP600 main control roem 5 - ,

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habitability system TS. The input was provided with a mark up of Westinghouse TS 3.7.6.

~J  ; incorporation of the, staff mark-up of TS 3.7.6 into the AP600 technical specifications,is' , j r o, considered a final safety evaluation report (FSER) open item. The FSER open item number 'v ~~

i ; and associated mark-up are included in the enclosures to this letter. ,,

s

  • i' y.

~ If you have any questions regarding this ms.tter, you may contact me at (301) 415-1141.

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Sincerely, -

[< original signed by:

William C. Huffman, Project Manager 7 Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation -

Docket No.52-003

Enclosures:

As stated gpKF cc w/ encl: See next page DISTRIBUTION:

Docket File PDST R/F JRoe

' 9g PUdLIC DMatthews TQuay 33 TKenyon WHuffman JSebrosky JNWilson DScaletti JMoore,0-15 B18 WDean,0-5 E6 ACRS (11) _ MReinhart,0-13 H15 AChu,0-13 H15 WBeckner,0-13 H15 JRaval,0-8 D1 CCarpenter,0-8 D1 TMarsh,0-8 D1 DOCUMENT NAME: A:TS-4-OI.SER To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy

.with attachment / enclosure "N" = No copy OFFICE - PM:PDST:DRPM BC:TSBA5PR D--

PDST:DRPM NAME WCHuffmanSWs WBeckner WDP> ' TRQuay $2<t ,

DATE 12/Jld97 12/ S /97 12/17/97 OFFICIAL RECORD COPY-9001050300 971217 sa a a sai s PDR E

ADOCK 05200003 PDR lll is .als ll, .- l.ln., lll lllllasa

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1

  • l Mr. Nicholas J. Liparuto Docket No. 52 003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre _

Mr. Russ Bell Advanced Plant Safety & Licensing Senior Project Manager, Programs Westinghouse Electric Corporation Nuclear Energy institute Energy Systems Business Unit 1776 l Street, NW P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706 Ms. Cindy L. Haag Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Soarch Associates Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Dr. Craig D. Sawyer, Manager Advanced Reactor Programs Mr. Sterling Franks GE Nuclear Energy U.S. Department of Energy 175 Curtner Avenue, MC-754 NE 50 San Jose, CA 95125 19901 Germantown Road Germantown, MD 20874 Mr. Robert H. Buchholz GE Nuclear Energy Mr. Frank A. Ross 175 Curtner Avenue, MC-781 U.S. Department of Energy, NE-42 San Jose, CA 95125 Office of LWR Safety and Technology 19901 Germantown Road Barton Z. Cowan, Esq.

Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Charles Thompson, Nuclear Engineer Pittsburgh, PA 15219 AP600 Certification NE 50 Mr. Ed Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenue Mr. Robert Maiers, P.E. Palo Alto, CA 94303 Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 l

- .~. - - - -. .- . . . -

f SER OPEN ITEM ASSOCIATED WITH AP600 TECHNICAL SPECIFICATION 3.7.6 410,414F. LCO 3.7.6. Main Control Room Habitability System (VES)

The staffs comments on the main control room habitability system technical specification are reflected in the mark-up to TS 3.7.6 provided in enclosure 2 to this letter. Westinghouse is requested to incorporate these changes. This is an open item.

Enclosure 1

3-l ; _-

Main Control- Room Habitability System (VES) ,

3.7.6 - _

-3.7 = PLANT SYSTEMS 3.7.6 Main Control-Room Habitability System (VES)

LCO 3.7.6 Two Main Control Room-(MCR) Habitability System trains shall  !

- be OPERABLE. i APPLICABILITY: MODES 1, 2. 3. and 4  :

During movement of irradiated fuel assemblies.

1 ACTIONS-CONDITION REQUIPED ACTION COMPLE110N TIME A. One VES train A.1 Restore VES train to 7 days inoperable. OPERABLE status.

B. MCR air temperature B.1 Restore MCR air 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> '

not within limit. temperature to within limit.

C. Loss of integrity of C.I. Restore MCR pressure 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> MCR pressure boundary to OPERABLE boundary, status *

.)-

D. Required Action and 0.1 Be in MODE 3. . 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion g gg9 jg gous.S Time of Conditions A. g .32--A# '

B. or C not met in MODE 1. 2. 3. or 4. 0.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E. Required Action and E.1 Suspend CORE Imediately associated Completion ALTERATIONS.

Time of Conditions A.

B, or C not met- AND during movement of irradiated fuel. E.2 Suspend movement of Immediately irradiated-fuel assemblies.

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3.7 12 08/97 Amendment 0 Enclosure 2

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Main Control Room Habitability System (VES) 3.7.6~

ACTIONS (continued)'- ,

CONDITION- I COMPLETION TIME

'iOUIRED ACTION

~

F. Two-VES trains F.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> inoperable in MODE 1, 2, 3, or 4.

F.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> g

F.3 Restore one VES train to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OPERABLE status.

G. Two VES trains G.1 Suspend CORE Imediately inoperable during A'.TERATIONS.

movement of-irradiated fuel. @

G.2 Suspend movement of Immediately irradiated fuel assemblies, 3.7 13 08/97 Amendment 0 b AP60oi ow=,cr.. m>a.0

.- . Main Control Room Habitability System (VES)

~I 3.7.6 d . t SURVEILLANCE REQUIREMENTS-SURVEILLANCE FREQUENCY g:-

SR 3.7.6.1 Verif Control Room air temperature 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

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SR 3.7.6.2 Verify that the compressed ah: storage m. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 4 tanks are pressiirized to [> 3400 psig).

SR 3.7.6.3 Verify that each VES t..r delivery In accordance isolation valve is OPERABLE. with the Inservice Testing Program

^

. SR 3.7.6.4 Verify that each VES air header manual 31 days isolation valve is in an open position.

SR 3.7.6.5 Verify _that all ain Control Room 24 months isolatio re OPERABLE and will ggye5 close upon receipt of an actual or simulated actuation signal.

SR 3.7.6.6 Verify that each VES pressure relief In accordance isolation valve within the MCR pressure with the boundary is OPERABLE. Inservice Testing Program SR 3.7.6.7 Verify that each VES pressure relief 24 months damper is OPERABLE.

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(continued) g600,, ,_

3.7 14 08/97 Amendment 0

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' + * .- . Main Control Room Habitability System (VES)

' 3.7.6 SURVEILLANCE REQUIREMENTS--(continued)

SURVEILLANCE .. FREQUENCY

-SR 3.7.6.8 Verify that the self contained pressure In accordance

-regulating valve in each VES train is with the.

OPERABLE. Inservice Testing Program

-SR 3.7.6.9 Verifv thaf one VES air delivery train

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maintains (positivepressureinthe /p

-ju (~' y p MC relati"ve to the adjacent areas at /gy(jof 4 s wf AJcb/y fel /r.

the reauired air addition flowret[ f.r. sed' eir j[8 64 veld (ES %*jyf _

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Main Control Room Emergency Habi% ability System B 3.7.6 B'3.7f PLANT SYSTEMS B 3.7.6 Main Control Room Emergency Habitability System BASES BACKGROUND The Main Control Room Habitability System (VES) provides a *

plant following an uncontrolledprotected environment from

. lease of radioactivity.

The system is designed to operate following a Design Basis Accident (DBA) which requires protection from the release of radioactivity. In these events, the Nuclear Island Non Radioactive Ventilation System (VBS) would continue to-function if AC power is available. If AC power is lost or a High 2 main control room (NCR) radiation signil.is received, the VES is actuated. The major functions of the VES are:

1) to provide forced ventilation to deliver an adequate supply of breathable air for the NCR occupants: 2) to ,

provide-forced ventilation to maintain the NCR at a 1/8 inch' '

water gauge positive pressure with respect to the surrounding areas; and 3) to limit the temperature increase of the MCR equipment and facilities that must remain functional passive during heat sinks.m accident, via the heat absorption of i

g pg.ns/e as, 2 The VES consists of two redund c conM d g g ) -+ compressed air storage tanks andqssocia ed valves, pising.t c

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.o p oM gg/ M 3 and instrumentation. Each set of tanks conta'ns enoug1-breathable air to supply the required air flow to the MCP. cs' -/

for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The VES system is designed to mainte 1 CO, concentration less than 0.5% for up to 11 HCR occupunts with both trains operating. With one train L

V ooerating. VESi r . = S ., ._ --_..m.. ......_.__..rj C = te L m.n : ~+ . ;.M a1ntains CO concentration less tian 1.0% for up to occupants.

2 Sufficient structure thermal mass exists in ine surrounding concrete

' ,,, a the haa neluding walls, ceiling and floors) to absorb

q'b bel nerated inside the MCR. which is initially at or wor t Heat sources inside the MCR include operator ions, emergency lighting and occupants. Sufficient insulation is provided surrounding the MCR pressure boundary to preserve the minimum required thermal capacity of the heat sink. The insulation also limits the heat gain from ,

the adjoining-areas following the loss of VBS cooling.

1 (continued) b AP60 .0

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Main Control Room Emergency Habitability System B 3.7.6 9

, BASES

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BACKGROUND

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.r The compressed air storage tanks are initially pressurized to 3400 psig. During operatior, of the VES, a self contained

"*,c, per I, g. pv us V6 'I' pressure regulating valve maintains a constant downstream pressure regardless of the upstream pressure. An orifice g p /2. [*" g J .rdC ' downstream of the regulating valve is used to control the gj/h, /g6,/ g4 air flow rate into the MCR. The MCR is maintained at a 1/8 p/s/6 ', d p , inch water gauge sitive pressure. to minimize the w f, & filtration of a rborne contaminants from the surrounding onL y C* ll#'

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%U APPLICABLE @ . W .. A d. M s v com)ressed air storage tanks are sized ouIgjt agCk SAFETY ANALYSES sucn tnat each set of ants has a combined capacity that 4I l

. provides at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of VES operation.

9A' Operation of the VES is automatically initiated by either of two safety related signals: 1) undervoltage to Class 1E battery charger, or 2) high 2 particulate or iodine radioactivity.

In the event of a loss of all AC power, the VES functions to ,

provide ventilation, pressurization, and cooling of the MCR pressure boundary.

In the event of a high level of gaseous adioactivity outside of the NCR, the VBS continues to operate to provide pressurization and filtration functions. The HCR air supply downstream of the filtration units is monitored by a safety c P*" g ' " ' " g-- "

related radiation dete. tor. U -r--d! - me te-w P 4o undervn1t w= + '"--- or hiijh 2 particulate or iodine radioactivity setpoint, a safety related signal is generated to isolate the NCR from the VBS and to initiate air flow from the VES storage tanks.

Isolatiort ol the VBS consists of closin fety related L"/VE S (d Tryin the supply and exhaus at penetrate the nCR pressure boundary. VES air f cw is initiated by a safety related signal which opens the isolation valves in the VES supply lines.4 ,

The VES functions to mitigate a DBA or transient that either assumes the failure of or challenges the integrity of the fission product barrier.

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Main Ccurul Room Emergency Habitability System

, B 3.7.6 1

. . 1 BASES 4

-:APPLICABLEJ The VES satisfies the' requirements of Criterion 3 of the ~NRC _  !

' SAFETY ANALYSES- Policy Statement,  ;

z(continued)

-LCO- ~ The VES. limits the MCR temperature rise and' maintains the MCR at a positive pressure relative to the surroundi.1g._

en'.4 onment.

Two independent and redundant.VES trains are required to be c OPERABLE to ensure that at least-one is available, assuming a single failure disables the other train. ,

The VES is considered OPERABLE when the individual componentt necessary to deliver a supply of breathable air to the MCR are OPERABLE in both trains. This includes components listed in SR 3.7.6.2 through 3.7.6.8, In addition, the MCR pressure boundary must be maintained, j including the integrity of the walls, floors.' ceilings,' duct work, electrical and mechanical penetrations, and access '

doors.

o APPLICABILITY The VES is required to be OPERABLE in MODES 1, 2, 3. and 4

' and during movement of irradiated fuel because of the potential for a fission product release following a DBA.

i The VES is not required to be OPERABLE-in MODES 5 and 6 when irradiated fuel is'not being moved because accidents resulting in fission product release are not postulated.

ACTIONS J

A When one VES train is inowrable, action .is required to restore the system to OPERABLE status. A' Completion Time of 7 days is permitted to restore the train to OPERABLE status before action must be taken to reduce power. - The Completion Time of 7. days is based on engineering judgment, considering the low probability of an accident that would result in a significant radiation release from the fuel, the low probability of not containing the radiation, and that the

remaining train can provide the required capability.

L 4 .

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Main Control Room Emergency Habitability System B 3.7.6 BASES-ACTIONS 8.1 (continued)

When the main control room air temperature is outside the acceptable range during VBS operation, action is required to restore it to an acceptable range. A Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is permitted based upon the availability of temperature indication in the MCR. It is judged to be a sufficient amount of time allotted to correct the deficiency in the nonsafety ventilation system before shutting down.

~

_C,,1 If the MCR pressure boundary is damaged or otherwise degraded, action is required to restore the integrity of the pressure boundary and restore it to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is permitted based upon operating experience. It is judged to be a sufficient amount of time allotted to correct the deficiency in the prese e boundary.

D.1 0.

/^

In MODES 1, 2, 3 or 4 if Conditions A, B, or C cannot be restored to OPERABLE status within the required Completion Time, the plant must be placed in a MODE that minimizes acci nt risk. This is done by entering MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 within 36 ho h ,&ggp J E.1 and E.2 o n c{ H o d t f Cao rin movement of irradiated fuel assemblies. if the y M-^m= t"3 treir. cx .et M rat:r:d +n nogof3LE m+ng Kt quis trj hu.lons A.1, B.1, or L.1 cannot be completed witn1n the required Completion Time, the movement of fuel and core alterations must be suspended. Performance of Required Action E.1 and E.2 shall not preclude completion of actions to establish a safe condition.

F.1. F.2 and F.3 p n/

If both VES trains are inoperable in MODES 1, 2, 3 or 4, the VES may no capable of performing the ir. tended functi d must be brought to MODE 4, where the fg OC(TNf; Nd yI / probabilit a consequences of an event are minimized, and one VES tr n must be restored to OPERABLE status within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. This 15 done by entering MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> P.4 0)E and MODE 4 withi hours.

(continued)

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Main Control Room Emergency Habitability System B 3.7.6 BASES ACTIONS G.1 and G.2 (continued)

During movement of irradiated fuel assemblies with two VES trains inoperable, the Required Action is to immediately suspend activities that present a potential for releasing radioactivity that might enter the NCR. This places the plant in a condition that minimizes risk. This does not preclude the movement of fuel to a safe position.

SURVElli.ANCE SR 3.7.6.1 REQUIREMENTS The MCR sir temperature is checked at a frequency of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to verify that the VBS is performing as required to maintain the initial condition temperature assumed in the safety analysis, and to ensure that the MCR temperature will ,

3 not exceed the required conditions after loss of VR9 g cooling. The surveillance limit of M8F is the id.Ml-Cb .ri"y, g - rQ The safety analysis v{alue of 80'F includes a P4f g, 2*fmea=surement uncertainty. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is ydpl

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acceptable based on the availability of temperature indication in the NCR.

h SR 3.7.6.2 N , p .g* Verification every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that compressed air storage p obfl tanks are pressurized to [> 3400 psig) is sufficient to ensure that there will be an adequate supply of breathable Op air to maintain MCR habitability for a wriod of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The Frequency of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is based on t1e availability of pressure indication in the MCR.

SR 3.7.6.3 VES air delivery isolation valves are required to be verified as OPERABLE. The Frequency required is in accordance with the Inservice Testing Program.

SR 3.7.6.4 VES air header isolation valver are recuired to be verified own at 31 day intervals. This SR is cesigned to ensure tnat the pathways for supplying breathable air to the MCR are available should loss of VBS occur. These valves should be closed only during required testing or maintenance of downstream components, or to preclude complete depressurization of the system should the VES isolation valves in the air delivery line open inadvertently or begin to leak. (continued)

@ AP600 teotsteamspecst6030704 r07 082497 B 3.7 30 08/97 Amendment 0

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Main Control Room Emergency. Habitability System B 3.7.6 BASES SURVEILLANCE SR 3.7.6.5 /V9],$

REQUIREMENTS (contingsd) Verification that all VBS isolation are operable and will actuate upon demand is require'&;ic. d every 4 months to ensure that the HCR can be isolated upon loss of VBS operation.

SR 3.7.6.6 Vee 4fication that each VES pressure relief isolation valve within the NCR pressure boundary is OPERABLE is required in accordance with the Inservice Testing Program. The SR is used in combination with SR 3.7.6.7 to ensure that adequate vent area is available to mitigate NCR overpressurization.

SR 3.7.6.7 Verification that the VES pressure relief damper is OPERABLE is required at 24 month intervals. The SR is used in combination with SR 3.7.6.6 to ensure that adequate vent area is available to mitigate NCR overpressurization.

SR 3.7.6.8 Verification of the operability of the self contained pressure regulating valve in each VES train is required in accordance with the Inservice Testing Program. This is done to ensure that a sufficient supply of air is provided as required, and that uncontrolled air flow into the NCR will not occur. -

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g 3, SR 3.7.6.9 g y j,7, g,g a-[ '

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. The system performance test demonstrates that tie MCR 3 e f/td.(" fc d f.V o E S , /p/ M "

r.eu . pressurization assumed in dose analysis is maintained.

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. _ _ _ _ _ .__-_a___L__--____________-____

, Main Control Room Emergency Habitability System

,. , B 3.7.6 BASES (continued)

REFERENCES 1. AP600 SSAR. Section 6.4. " Main Control Room Habitability Systems.*

2. AP600 SSAR. Section 9.4.1. " Nuclear Island Non Radioactive Ventilation System."
3. SECY.95 132. " Policy and Technical Issues Associated With The Regulatory Treatment of Non Safety Systems (RTNSS) In Passive Plant Designs (SECY 94 084)." May :.J. -

1995.

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