ML20062E538

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Responds to 781031 & 761124 NRC Ltrs Requesting Addl Info Re Pump & Valve Testing Insvc Progs.W/Encl Oversize Drawings Available in Central Files Only
ML20062E538
Person / Time
Site: Calvert Cliffs  
Issue date: 11/20/1978
From: Lundvall A
BALTIMORE GAS & ELECTRIC CO.
To: Reid R
Office of Nuclear Reactor Regulation
References
NUDOCS 7812080125
Download: ML20062E538 (9)


Text

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i B ALTIMORE G AS AND ELECTRIC COMPANY P.O. B O X 1475 B A LTIM O R E. M A R YL A N D 2120 3 Antwun C. Lumovatt,Ja.

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November 20, 1978 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D.C.

20555 ATTENTION:

Mr. Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors

SUBJECT:

Calvert Cliffs Nuclear Unit No.1, Docket No.f.Palerglant 50-317 Unit No. 2, Docket No.'50-318

.[nservice Test Program

REFERENCES:

(a) NRC letter dated 10/31/78 from Mr. R. W. Raid to Mr. A. E. Lundvall, Jr.

(b) BG&E letter dated 6/8/78 from Mr. A. E. Lundvall, Jr.,

to Mr. R. W. Reid (c) BG&E letter dated 8/30/78 from Mr. A. E. Lundvall, Jr.,

to Mr. R. W. Reid (d) NRC letter dated 11/24/76 from Mr. D. C. Ziemann to Mr. A. E. Lundvall, Jr.

GENTLEMEN:

As requested by Reference (a), the following infonnation is hereby submitted:

PUMP TESTING PROGRAM 1.

All Note 1 parameters are recorded in accordance with IWP-6240.

2.

The emergency diesel transfer pumps are not provided with an emergency power source and therefore are not within the scope of IWP-1100.

3.

The emergency diesel air starting valves are tested weekly and h[

areincluded in the IST program categorized B.

They were erro-neously omitted from References (b) and (c).

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N.R.T.Reid

' N;vember 20, 1978 VALVE TESTING PROGRAM -

GENERAL COMMENT

S AND OUESTIONS l.

Unit i valve notes included in Reference (b) and Unit 2 valve notes included in Reference (c) are equally detailed and apply only to their respective Inservice Test Programs.

2.

Three copies each of prints M-53 and M-68 are attached.

3.

All power operated valves classified ASME class I, II, or III.

Category A or B subject to the exclusions of IWV-1300 are being stroke time tested. Limiting stroke times for all such valves are specified in References (b) and (c).

4 All power operated valves listed in References (b) and (c) re-ceive a check of valve position indicators per IWV-3300.

5.

All valve position and operational test results are recorded in accordance with IWV-6230.

VALVE TESTING PROGRAM - SPECIFIC OUESTIONS A.

High Pressure Safety Injection System Low Pressure Safety Injection System containment spray System 1.

a.

SI-340 is Categorized A/C in References (b) and (c).

b.

SI-330 is Categorized A/C vice C as is erroneously stated in References (b) and (c).

c.

SI-215, 225, 235, 245, 217, 227, 237, and 247 were correctly Categorized C in References (b) and (c). Since these valves are not containment isolation valves limiting seat leakage to a specific maximum amount in the closed position is not im-portant to fulfillment of that function. However per our discussions with Vic Nerses (NRC) on 11/9/78 we will re-ex-amine these valves to detemine if seat leakage measurements are required to insure that the valves perfom their " Pres-sure Isolation Functions."

2.

SI-316, 326, 330, and 340 cannot be full stroke tested without spraying the containment with contaminated water. Aside from the contamination aspect, electrical equipments and insulation within the containment would be damaged.

3.

SI-455 is Categorized A/E vice E as was erroneously stated in References (b)and(c).

4.

The containment sump does not normally have a water level in-l ventory. SI-4148 and SI-4149 cannot be full stroked without j

first flooding the containment floor with water. Both valves are partial stroked at 9 month intervals as prescribed by IWV-3520.

Mr. R. W. R31d N:vember 20, 1978 5.

Stroke testing SI-4193 through SI-4198 during plant operation would require spraying water onto the charcoal filter beds thereby destroying them.

6.

No requirement to remove power from SI-651 or SI-652 exists.

7.

SI-661 is correctly Categorized B as limiting seat leakage to a specific maximum amount is not required for fulfillment of its function.

8.

Category C a.

22 LPSI PP min. flow return check (SI-451) is Categorized C in Reference (c).

Category E a.

22 LPSI PF shutdown cooling suction isolation (SI-440),

22 LPSI PP normal suction isolation (SI-432), and 22 CS header isolation (SI-325) are Categorized E in Reference (c).

~

b.

The below listed valves are properly not included in Reference (c) as they are utilized for maintenance only and are therefore excluded from the IST program by IWV-1300. However we were informed by Vic Nerses (NRC) on 11/9/78 that the NRC Staff reconnends inclusion of these valves in the IST program. To comply with this request we will add the below listed valves to our IST program Categorized E.

SI-447 21 LPSI PP discharge SI-449 21 LPSI PP min flow return isolation SI-311 21 CS PP suction isolation SI-317 21 CS spray nozzle isolation SI-450 22 LPSI PP min. flow return isolation SI-435 22 LPSI discharge isolation SI-327 22 CS spray nozzle isolation SI-423 21 HPSI PP min. flow return isolation SI-470 21 HPSI PP suction isolation SI-428 21 HPSI PP discharge isolation SI-421 22 HPSI PP min, flow return isolation SI-411 22 HPSI PP suction isolation SI-414 22 HPSI PP discharge isolation SI-425 23 HPSI PP min. flow return isolation SI-402 23 HPSI PP suction isolation SI-406 23 HPSI PP discharge isolation SI-4950 22 Cntmt charcoal filter dousing header isolation SI-4959 22 Cntmt charcoal filter dousing header isolation SI-4949 21 Cntmt charcoal filter dousing header isolation SI-4958 21 Cntmt charcoal filter dousing header isolation i

SI-4951 23 Cntmt charcoal filter dousing header isolation SI-4960 23 Cntmt charcoal filter dousing header isolation 1

Mr. R. W: Reid November 20, 1978 9.

SI-464 and SI-465 may be found on prints M-73 (U-1) and M-461 (0-2) at co-ordinates A-5.

SI-475 may be found on the same prints at co-ordinates C-7.

The three valves are not listed in either References (b) or (c) as they are not classified ASME Class I, II, or III.

i

10. SI-352 SI-325, SI-432, SI-440, and SI-450 are all listed in i

Reference (c).

B.

Service Water Cooling System 1.

SRW-117 through SRW-124 are not nonnally locked and are there-fore properly Categorized B in References (b) and (c).

2.

SRW-1598 and SRW-1599 are correctly listed as service water inlet and outlet isolation valves for 12 spent fuel pool heat exchanger inReference(c). SRW-1596 and SRW-1597 are correctly listed as service water inlet and outlet isolation valves for 11 spent fuel pool heat exchanger in Reference (b).

3.

SRW-1600, SRW-1637, SRW-1638, and SRW-1639 isolate service water to all service water cooled equipments in the turbine building.

Components cooled include instrument and plant air compressces, lube oil coolers and numerous pumps. Cessation of cooling water to these components would result in their overheating with sub-sequent failure. This was recognized in Section 7.3.2.2 of the FSAR which indicates that the valves cannot be shut for test purposes during reactor operation.

4 The six manual isolation valves associated with coolir.g water to emergenc Reference (y diesels 12 and 21 are properly not included in c) as they are utilized for maintenance only and are therefore excluded from the IST orogram by IWV-1300.

How-ever, we were infonned by Vic Nerses (NRC) on 11/9/78 that the NRC Staff reconsnends inclusion of these valves in the IST pro-gram. To comply with this request we will add the six valves to our IST program Categorized E.

5.

Category C a.

We concur with the NRC Staff position and will add the two i

check valves to our IST program Categorized C.

Category B

}

a.

2-SRW-1646-CV and 2-SRW-1645-CV are properly listed as Category B in Reference (c).

C.

Salt Water System 1

1.

SW-112 through SW-115 are not normally locked and therefore are properly Categorized B in References (b) and (c).

2.

Opening 1-SW-5149 dumps the discharge of 11 saltwater pump directly overboard thereby comoletly disabling 11 saltwater

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Mr. R. W. Reid N;vember 20, 1978 subsystem. Therefore the valve is not cycled durirg plant operation per guidance provided by Reference (d).

D.

Comoonent Cooling System 1.

The inline manual valves supplying cooling water to the HPSI and LPSI pumps are properly not included in References (b) er (c) as they are utilized for maintenance only and are therefore ex-cluded from the IST program by IWV-1300. However, we were in-formed by Vic Nerses (NRC) on 11/9/78 that the NRC Staff re-comends inclusion of these valves in the IST program. To comply with this request the valves will be added to our IST program Categorized E.

E.

Auxiliary Building Waste Process System 1.

EAD-5463 is listed in Reference (c).

F.

Chemical and Volume Control System Category E 1.

The boric acid tank outlet valves, boric acid pump suction ano discharge valves, charging pump suction and discharge valves, charging pump comon discharge valve, CYC-C19 manual bypass valve, CVC-519 downstream isolation valve, and CVC-518 down-stream isolation valve are properly not included in References (b) and (c) as they are utilized for maintenance only and are therefore excluded from the IST procram by IWV-1300. However, we were infomed by Vic Nerses (NRC) on 11/9/78 that the NRC Staff recomends inclusion of these valves in the IST program.

To comply with this request we will add the above listed valves to our IST program Categorized E.

Category C 1.

We concur with the NRC Staff position and will add the check valve bypassing CVC-519 and the volume control tank outlet check valve to our IST program Categorized C.

2.

The letdown heat exchanger relief valve (RV-345) is not included in the IST program since it is not classified ASME Class I, II, or III.

Category A 1.

Letdown control valve CVC-110P and CVC-110Q are not containment isolation valves and are not classified ASME Class I, II, or III. Therefore they are properly not included in the IST pro-gram.

G.

Steam Generator Blowoown System 1.80-113 through BD-124 no longer exist and are not included in either References (b) or (c).

Mr. R. W; Reid November 20, 1978 H.

Reactor Coolant System 1.

The quench tank demineralized water inlet checic valve is correctly identified as DW-251 in both References (b) and (c). DW-251 is not a containment isolation valve and is properly Categorized C.

Three manual isolation valves (DW-250, DW-280, DW-364) downstream DW-251 will be added to the IST program Categorized A/E.

2.

Thequenchtanknitrogeninletcheckvalve(N2-247)isnota containment isolation valve and is therefore properly Cat-egorized C.

3.

The pressurizer power operated relief isolation valves are utilized for maintenance only and are therefore excluded from the IST pro-gram by IWV-1300.

I.

Main Steam System 1.

The blowdown isolation valves B0-4010, BD-4012, 80-4013, and B0-4011 are not containment isolation valves and are therefore properly Categorized B in References (b) and (c).

2.80-113 through BD-124 no longer exist and are not included in either Reference (b) or (c).

3.

Category B We concur with the NRC Staff position and will add MOV-4070 and MOV-407) to the IST program Categorized B.

Category C We concur with the NRC Staff position and will ada m Nur auxiliary feed pumo steam supply check valves to the n r program Categorized C.

Catecory E The manual steam isolation valves supplying steam to the auxiliary feed pumps are utilized for maintenance only and are therefore excluded from the IST program by IWV-1300.

However, we were infomed by Vic Nerses (NRC) on 11/9/78 that the NRC Staff recomends inclusion of these valves in the IST program. To comply with this request we will add the valves to our IST program Categorized E.

J, Condensate and Feedwater System 1.

The auxiliary feed water pump discharge check valves are not partially stroked during operation as was erroneously stated in References (b) and (c).

Exercising these valves during l

Plant operation would require feeding hot steam generators with cold feedwater thereby themally shocking the auxiliary feed rings within the steam generators.

'r. R. W. R51d November 20, 1978 M

2.

We concur with the NRC Staff position and will add the auxiliary feed water regulating valves to the IST program Categorized B.

3.

The auxiliary feed water pump suction and discharge valves are utilized for maintenance only and are therefore excluded from the IST program b Vic Nerses (NRC) y IWV-1300. However, we were informed by on 11/9/78 that the NRC Staff recommends in-clusion of these valves in the IST program. To comply with this request we will add the valves to our IST program Categorized E.

K.

Spent Fuel Pool Cooling System 1.

The c~ontainment isolation valves on P&ID M-58 are included in the IST program Categorized A/E. They were erroneously omitted from References (b) and (c).

2.

Valves on P&ID M-58 identified in References (b) and (c) are classified ASME Class III and are properly included in the IST program. The spent fuel pool pumos suction and d'scharge valves are utilized for maintenance only and are excluded from the IST program by IWV-1300.

3.

No spent fuel pool cooling system valves are listed in Reference (c). These valves are correctly categorized in Reference (b).

i L.

Gas Analysis System 1.

The twenty eight containment isolatica valves on P&ID M-463 are included in the IST program Categorized A/E. They were erroneously omitted from References (b) and (c).

Should you have further questions regarding our cump and valve inservice test program we would be pleased to discuss them with you.

Very truly yours, A. E. Lundvall, Jr.

Vice President Supply AEL/JTC/gfc Enclosures L

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