ML18038A271

Forwards Application to Use Alternative to 10CFR50.55(a) Requirements Involving Temporary Repair of Leak on Svc Water Discharge Piping of Facility.W/One Oversize Figure

ML18038A271
Person / Time
Site:	Nine Mile Point
Issue date:	08/25/1987
From:	Mangan C NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
(NMP1L-0179), (NMP1L-179), NUDOCS 8709010230
Download: ML18038A271 (13)

Text

REGULATORY IFORMATION DISTRIBUTION SY

'EM (RIDS>

1 r "ACCESSION NBR: 8709010230 DOC. DATE: 87/08/25, NOTARIZED:

YES DOCKET 0 FACIL: 50-220 Nine Mile Point Nuclear Stations Unit ii" Niagara Poee 05000220 AUTH. NAME AUTHOR AFFILIATION MANQANe C. V.

Niagara Mohaek Power Corp.

RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk>

SUBJECT:

Forwards application to use alternative to 10CFR50. 55(a>

requirements involving temporary repair of leak on svc eater discharge piping of-facility. W/one oversize drawing.

DISTRIBUTION CODE:

A047D COPIES RECEIVED: LTR l ENCL g SIZE:

TITLE:

OR Submittal:

Inservice Inspection/Testing NOTES:

RECIPIENT ID CODE/NAME PD1-1 LA BENEDICT' INTERNAL: AEOD/DOA ARM/DAF/LFMB NRR/DEST/MTB OQC/HDSi RES/DE/EIB EXTERNAL:

LPDR NSIC COPIES LTTR ENCL 1

0 1

1 1

1 0

1 1

0 1

1 1

1 1

1 RECIPIENT ID CODE/NAME PD1-1 PD HAUQHEYz M AEOD/DSP/TPAB NRR/DEST/MEB NRR /P MAS/ILRB 01 NRC PDR COPIES LTTR ENCL 5

5 1

1 1

1 1

1 1

1 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 20 ENCL 17

J I =- I

V NIAGARA U MOHAWK NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474-1511 August 25, 1987'NMPlL 0179)

U.S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C.

20555 Re:

Nine Mile Point Unit 1

Docket No. 50-220 DPR-63 Gentlemen:

Attached please find an application to use an alternative to the requirements of 10 CFR 50.55a.

The requested alternative involves a temporary repair of a leak on the. service water discharge piping of Nine Mile Point Unit 1.

Very truly yours, NIAGARA MOHAWK POWER CORPORATION C.

V.

Mang Senior Vice President PEF/pns 3460G Attachment xc:

Regional Administrator, Region I Mr. R. A. Capra, Director Mr. R. A. Benedict, Project Manager Mr.

W. A. Cook, Resident Inspector 8709010230 8

PDR ADDCK 0500

~D2R P

I'r C

E

UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of

)

)

NIAGARA MOHAWK POWER CORPORATION

)

)

(Nine Mile Point Nuclear Station Unit No.

1

)

Docket No. 50-220 APPLICATION TO USE AN ALTERNATIVE TO THE REQUIREMENTS OF 10 CFR 50.55(L Pursuant to Section 50.55a(a)(3) of the Commission's Regulations (10 CFR 50.55a(a)(3)),

Niagara Mohawk Power Corporation, holder of an operating license for the Nine Mile Point Nuclear Station Unit 1 (Docket No. 50-220),

hereby makes application for authorization to use an alternative to the requirements set forth in Section 50.55a(g)(4) of the Commission's Regulations.

Section 50.55a(a)(3) states that:

"Proposed alternatives to the requirements of paragraphs (c), (d), (e), (g) and (h) of this section or portion thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation.

The applicant must demonstrate that (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements of this section would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety."

3460G

Section 50.55a(g)(4) requires that throughout the service life of a nuclear power facility, components which are classified as ASME Code Class 1,

2 and 3

shall meet the requirements set forth in Section XI of the Code.

Niagara Mohawk proposes to implement the following alternative to 10 CFR 50.55a(g)(4) which will provide an acceptable level of quality and safety:

Install a

temporary sleeve over a through-wall leak in the service water discharge bypass line.

Attachment A to this application demonstrates that the proposed alternative to Section 50.55a(g)(4) provides an acceptable level of quality and safety.

Attachment A also demonstrates that compliance with 10 CFR 50.55a would, in this case, result in hardship and unusual difficulties without a compensating increase in the level of quality and safety.

WHEREFORE, Applicant respectfully requests that the proposes alternative to the requirements of 10 CFR 50.55a(g)(4),

be authorized by the Commission.

NIAGARA MOHAWK POWER CORPORATION By Senior V'

President Subscribed and sworn to before me on this g5 day of August 1987.

MARY FRATESCH1 kotary Public In the State of tfew York Quallfled ln Onondaga County ffo. 4797/~

My Commlsslon Errlrlrea~30, 19S~

NO RY PUBLIC 3460G

1

NIAGARA MOHAHK POHER CORPORATION NINE MILE POINT UNIT 1

DOCKET NO. 50-220 DPR-63 ATTACHMENT A Descri tion of the Problem A leak has developed in the service water discharge bypass line downstream from blocking valve 72-92, as shown in Figure 1.

The apparent cause of the leak is due to erosion/corrosion.

The leak has been isolated by closing the blocking valve.

The bypass piping penetrates the Reactor Building floor directly below blocking valve 72-92.

The leak is located in the area of the pipe which is in the floor penetration sleeve.

Due to the access restrictions, it is not possible to perform a code repair by removing the indication and performing a weld repair of the leak.

Therefore, the defective section of piping will have to be cut out and replaced.

The Service Hater system provides lake water for cooling the Reactor Building closed loop cooling systems.

Because the Reactor Building Closed Loop Cooling system is always required to operate (i.e., certain heat loads are always present), it will be difficult to cut out this section of bypass piping and replace it during normal operation or during a brief shutdown.

The flow in the main service water discharge line through temperature control valve TCV 72-146 will affect the welding.

In addition, the bypass line would have to be used to provide essential cooling to the RBCLC system if the main service water discharge valve (TCV 72-146) became inoperable.

A permanent code repair could be more safely/effectively performed toward the end of a refueling and maintenance outage.

The decay heat load would be significantly reduced, thus permitting flow in the service water discharge piping to be reduced to a minimum.

Therefore, Niagara Mohawk requests approval to temporarily repair the leak in the service water discharge bypass line by welding a sleeve around the section of the pipe in the floor penetration.

The sleeve will be split fitted on the pipe and the longitudinal split welded.

The sleeve will then be slid up through the floor penetration and welded top and bottom.

This sleeve will prevent any leakage.

A permanent code repair will be made during the next scheduled refueling outage in Spring 1988.

S stem Desi n

The Service Hater System provides lake water for cooling the Reactor Building Closed Loop Cooling Systemand other non-safety related systems as described in Section X.F of the Nine Mile Point Unit 1 Final Safety Analysis Report.

In the event of the loss of offsite power, the service water pumps would be unavailable.

Under these conditions, emergency service water pumps would be available to provide cooling water to the Reactor Building Closed Loop Cooling heat exchangers.

The emergency service water pumps are connected to powerboards which are supplied power from the diesel generators if their normal supply fails.

The Reactor Building Closed Loop Cooling System, in turn, provides cooling water to the following major components:

3460G

~ '

fuel pool heat exchangers*

instrument air compressors*

electric feedwater pumps*

condensate pumps" feedwater booster pumps*

control room, *laboratory and administrative building air conditioning equipment recirculation pump coolers cleanup system non-regenerative heat exchangers reactor building equipment drain tank cooler drywell air coolers waste disposal system heat exchangers shutdown cooling system heat exchangers and pump coolers See Section X.D of the Nine Mile Point Unit 1 Final Safety Analysis Report for a'dditional information regarding the design of the Reactor Building Closed Loop Cooling System.

The operation of the Reactor Building Closed Loop Cooling heat exchangers is controlled by automatic temperature control valves TCV 72-146, 70-137A and 70-1378 as shown in Figure 1 (attached).

Valves 70-137A and B operate in tandem to regulate RBCLC cooling water flow to the heat exchangers.

Excess flow is diverted to the discharge header.

Valve TCV 72-146 controls the'ervice water discharge flow from the'heat exchangers.

These three valves work in conjunction to maintain a preselected RBCLC heat exchanger outlet temperature.

A bypass line is provided around TCV 72-146.

During normal operation, TCV 72-146 is open and blocking valve 72-92 in the service water discharge bypass line is closed However, during the summer months, when the lake temperature is at its highest temperature, blocking valve 72-92 is opened to increase service water flow thru the Reactor Building Closed Loop Cooling heat exchangers.

The increased flow provides additional cooling required to maintain the Reactor Building Closed Loop Cooling System discharge temperature.

Justification The leak in the piping is downstream from manual blocking valve 72-92.

Therefore, if the leak were to reoccur, it could be isolated by manually closing the blocking valve.

The service water discharge piping is a low pressure and temperature line (design pressure/temperature is 110 psig/

120'F).

The pipe wall thinning is due to erosion/corrosion which is a slow process.

Therefore, any additional erosion/corrosion will occur slowly over a

long period of time (i.e., years) and a catastrophic failure of the discharge piping is not likely to occur.

In addition, Niagara Mohawk proposes to monitor the service water discharge piping bypass line by daily visual inspections.

Any leakage from the bypass discharge piping wi 11 not prevent the service water and reactor building closed loop cooling systems from performing their safety functions.

However, the bypass line will be isolated if any leakage is detected.

Accordingly, the proposed alternative provides an acceptable level of quality and safety.

The plant shutdown necessary to implement a permanent repair constitutes a hardship without a compensating increase in the level of quality and safety.

• identifies essential safety related cooling load 3460G

t A

8 A

@+4'

t 30E j33HS O-ZZ OB I-O SERVICE WATER SHEET MI O'D 3 SERVICE WATER SHEET¹I

(& E-I SCREEN+

HOUSE 8

(sw-zz)

TESTS LEVE 72-21 TEST (Sw-70

~72-i

'2-22 ISW-261 O

,I.

~?2-18 E

~ce oe E

REACTOR BLDG SUPPLY I

C -180 27 -C SH. 2 (SW63)

(SW-60)

(SW 64)

(SW.65)

O R SSDT (SW 71¹)

Ps

~de

~PAL

+72 54

~2812 t )VB-III JHJ I

I TX N2 VAPORIZER UNIT C-I8014.C 1¹ (L&TER)

SHEET¹4 i

] 6LIND FLANSE FROM IESEL FIRE PUMP SIC 3 I

,\\

o (SW 316) 3 VJ 0 "'L (SW-314)

JJVD f1 O 3Ul p

AT:

ES w. 311)

VJ (SMI~

~

REACTOR 8 DG.

SERVICE WATER C -18027 C

SH.

2 l

4 Ul J

VJ OI-EMERGENCY SERVICE WATER TEST LEVER

~72-77 4 PA H 4-19D I9-SPAH Hl-&-1

-. 5IR AI N E RS IJ I

72 07 72 0&

C

&PAH (Sw e7)

A"189 (SW-704) 41-dPS 2 F I 72-OSA (SW.TO) 12

-OTA 72 (5%.70 (SW-68)

HdPA H (Sw-69) 3 O

(SW 71)

(SL¹66)

PI 72-57 PI 72-58 Iz (SV 7031 (SW'lol) 12 l-IJJ O

HJl-TEST LEVER

~ra-Te JRrd!a M)he.(E.

I C a((.

ha>

bREPV dl'tck DISCHARGE MANIFOLD SHEET ~ I F-6

+72-78 CV 72-146 16 12' VZO-137 12 16 E

70-137 Hl.&.Z COOL ING 72-135 70-22 Ao

~70- IS 13 T

WATER TI 72-134 70-21

~BR-6-3 CL-8 (HCLC-1017)

~BR 3 E-CL-Io <Hcic-1015)

Rtc Ao Vl LJ 70- 79 so go 70-78

~o go

~rO-SO so p

AO

~XI-14 ¹12 HEAT L&Jl 72 133 70 20

~70-13 VII EXCHANGERS AO'BR-6-3 E-CL 12(RCLC-1019) p AO AO TI At ERTHRE CARD

~70-86

~to 95 TO DRYWELLAIR COOLER SHEET 4 A-3 ELEV. 379L6 Ul Ec LZ

&U&/

,(

PM 4&U z

AO P+

cc Ml 4Z Io

¹ 12 72-03 I

UJ vc SX CL-14 x

AO'MERG.

SERV.

WATER PUMPS

¹U (SUCTION FROM PIT) lo

~TRH

~TI Hl-4-1 D340.

70-23(

E.

TSE 70-23 D VENT RBEDT FTYE 70-ZSB BR-6-3

'70- 141 PS 70 279 7CPO3

¹13

~BR 6-5 VENT 14

~~BG-3 DRAIN P

RBEDS HPZH

~70-oe 10 70-60 70-09 so AO TI

'70-18 PS70-278 70-02

~BR-6-5 VENT REACTOR BUILDING QE474 V

H/

RA L

RAM

~RA I

~RE Hi-29 ~RNOSS

~RNUB

~RNOZE FX 70-42

-E'-

MV/I 70-23A TX

.TE 7D-19 E

MU/Il 70-19A TE 70-28&

14

~IH

&Mix g

JU, OIX X

3'U(

&/p

+70-538 70-53 so AO FX 70-40 go AO AO'X 70-41 BRCO-5

(

~70-61((

SHUT DOWN Ud) IC L ~BR-GT-5 0

BR-CO-5 7D-54 70-57 AO

~0~IN NU.O IB o ~BR-GT-5 I

BRCO5 RSEDT

~BR-6-4 I

I

(

I I

L

(

(

I I

L

\\J I

c HJ l

VJ UJ I

UJ Ul vc O

I OI-JH Jc UJ s7oX j oz~n-a~

~

O vc Al UJ3Ul zII-A wO I

F 6 I IO 3

Fs 70-39 ~ZLII I

H I-4-1 E!R-G-6 (U U-9)

L" e-14*

6 14

~BR-6-3 DRAIN RBEDS Hwl-I I0" PI 70-59 VENT RBEDS 70- 16 PS 70- 277 70-01

~BR-6-5 70-08 7 DOS AO 70-04 Ao COOLING WATER PUMP GE c

~PS TO-VS I

I I

I 70-17A I

I PAL

-U-

~AL Hl-4-1

~zill

~BIOS U

Z i~Pc I

Pc iZOJJBBGGBT 7OJ)4 DA gc(

MO DC 70 94 AO AO R

70 94A

~gONAATlON ONL~

~70-52

~70-49 BE&& FJGHH.&&HHGG'HeG VI I NLFOI4 C, BR-67-5 I

I I

I L

THIS DWG WAS REVISED &

REDRAWN FROM DWG C l8022 C-SH. 2 DATED 5 7HSE REVISION l2 ACC NO 3I730 30o3 l8 0000 KV&U&JL&Q

'MPH&MT,

&1 ~

NIAGARASIOHAWK POTVER CORPORATION NINE II)LE POII T NUCLEJP 5 ATION Ul(IT IVO¹I

+ FURNISHED SY M.W. KELLOGG NOTES:

I) FOR DETAILS OF Rx VESSEL HYDRO HEAT-UP SYS., SEE DWG. C-18018-C)

SHT. 2.

/JO/

'/H/

I

• /&e ADDED REFERENCE NOTE PEH 4 BUILT. DCH HIVV-MOS21LGBGZ REVISED PGH FIELD Velll W

FICATIDH.

DV&J &ZDO.M FINAL AS BUILT PER IDT&l 2928 F ORIGINAL Ps'70 lce. 109.¹c LGFV IN PLACE R

MOVED Pe'70- 277,271 279 I

& LO VR TRIP MB 1921 S)o

-/174 27 "D fw¹IACLDI/e 70 7& w'VH 70.21 P

4 FBU'P GU&llelc&TIBH l&D.I'121 PHI Ac Ul NEW GVHICHEG Fe GGUIPM HV GU&LIF.

M 0, leZV GEVI&EB DIESEL FIRE HJMV IHT&R-ll& VER&&BURT <<0&~ DV Bc¹ Lwl 5

I RE'V ISED PER FIELD AS BUILT IHF A OEO DIESEL FIRE PUMP INTER(J'g TIE To ESVC PUMP ll M034071 SJ i CLOSED LOOP COC" (NG & SER

'CE WATER REACTOR & WASTE BLDG'S.

P &j D(AGRAlvll

/-

. 7-UJ-52 N

. 3-N2-Sl

-I 022-C SHEET 30F4