Text

Amends 101 & 103 to Licenses DPR-44 & DPR-56,respectively, Changing Tech Specs to Revise Testing Requirements for Snubbers & Permit one-time Relief from Functional Testing of Mechanical Snubbers
	ML20090B459
Person / Time
Site:	Peach Bottom
Issue date:	07/02/1984
From:	Rivenbark G; Office of Nuclear Reactor Regulation
To:	; Atlantic City Electric Co, Delmarva Power & Light Co, Philadelphia Electric Co, Public Service Electric & Gas Co
Shared Package
ML20090B463	List: ML20090B459; ML20090B476;
References
	DPR-44-A-101, DPR-56-A-103 NUDOCS 8407120495
	Download: ML20090B459 (50)
	v • d • e

-__

pwea,u l

. g) )

a%

UNITED STATES 7,

NUCLEAR REGULATORY COMMISSION

y WASHINGTON, D. C. 20555

%, +....J PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AhENDMENT TO FACILITY OPERATING LICENSE Amendment No. 101 License No. DPR-44 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated March 24, 1981, as supplemented by letters dated August 6, 1981, December 13, 1982, June 22, 1983, September 14, 1983, and January 26, 1984, complies with the standards and requirements of-the Atomic Energy Act of 1954, as amended (the Act), and the~ Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and. safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 -

of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:

l l

8407120495 840702 PDR ADOCK 05000277 i

P PDR l

.~-

i i

1

_2_

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.101, are hereby incorporated in the license.

PEC0 shall operate the facility in accordance with the Technical Specifications.

f-3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION t]G

-l(. 'u l=LI b

s George W. Rivenbark, Acting Chief Operating Reactors Branch No. 4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: July 2, 1984 l

i

I i

ATTACHMENT TO LICENSE AMENDMENT N0.101 FACILITY OPERATING LICENSE NO. DPR-44 i

DOCKET N0. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

Remove Insert 234a 234a 234b 234b 234c 234c 234d 234d 234e 234e 234f 234f 234g 234g 234h 234h 2341 2341 234j 234j 234k

- 234k 2341 2341 234m 234m 234n 234n 2340 234o 234p 234q 234r 234s 235a 235a 236a 236a 236b 236b l

l l

.._ ~. - - - - - _.

4 1

PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11.D. Shock Suppressors 4.ll.D. Thock Suppressors (Snubbers) on Safety Related (Snubbers) on Safety Related Systems Systems 3.ll.D.1 During all modes 4.ll.D.1

~

of operation all -

snubbers listed in Table Snubbers listed in Table 3.ll.D.1 shall be operable 3.11.D.1 shall be demonstrated except as noted in

' OPERABLE by performance 3.11.D.2 and 3.11.D.3 of the following augmented below.

inservice inspection program and the requirements of Specification 4.6.G.

3.11.D.2 During operation in the 4.11.D.2 cold shutdown or refueling modes, snubbers located on Snubbers listed in Table system required to be operable 3.ll.D.1 shall be visually shall be operable except inspected according to the as noted in 3.ll.D.3.

following schedule.

No. of Snubbers Next Visual Found Inoperable Inspection Durin'g Inspec-Period 3.ll.D.3 With one or more tion Period snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , replace or restore 0

18 me. + 25%

the inoperable snubber to the 1

12 me. T 25%

operable status and perform 2

6 me. T 25%

an engineering evaluation per 3,4 4 mo. T 25%

specifi cation 4.11.D.6.

If 5,6,7 2 mo. T 25%

these requirements cannot be 8 or more 1 me. T 25%

met, declare the supported system inoperable and follow the applicable Limiting The required inspection Condition for Operation for interval shall not be that System.

lengthened more than one step at a time.

The provisions for extending surveillance frequency included in Section 1.0 Defini-tions do not apply.

Snubbers may be categorized in two groups,

" accessible" or " inaccessible",

based on their accessibility for inspection during reactor operation. These two groups may be inspected independently according to the above schedule.

' Amendment No.33,101 234a-

7 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS e

e' J 3.11.D.4 Snubbers may be 4.11.D.3 added to saf ety related i

systems without prior The visual inspection License. Amendment to shall verify that 1) there are Table 3.11.D.1 no indications of damage or e

provided that a impaired operability, 2) attach-revision on Table ments are secure, and 3) there 3.11.D.1 is included is freedom of movament i with the next License if this can be verified j

Amendment request.

without disconnecting i

i, the snubber.

1 Snubbers which appear to be inoperable may be made operable for the purpose of establishing i

the next visual inspection interval, providing that 1) the cause of the rejection' is clearly established and remedied for that particular snubber and for other generically susceptable snubbers; and 2) the affected snubber is functionally tested in the as found condition and determined operable per specification 4.ll.D.7 or

~ 4.11.D.8, as applicable.

When the fluid port of a hydraulic i

snubber is found to be uncovered, the snubber shall be determined to be inoperable for the purpose of establishing the next visual inspection interval.

4.ll.D.4 Functional Test a) Once each operating cycle, t

l during shutdown, a representative sample of lot of each type of (mechanical or hydraulic) snubber shall be functionally tested either in l

place or in a bench test.

For every unit found to be inoperable an additional 10% of that type of snubber shall be functionally tested until no more failures are found or all snubbers of that type have been t e., ced.

The functional test re quirement for mechanical snubbers will not take effect AaemhGnt No.101

-234b

PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS until the first refueling outage commencing one year after approval, by the NRC, of this Technical Specification amendment.

b) The representative sample

~

selected for functional testing shall include various configurations, operating environments, sizes, and capacities of snubbers.

At least 25% of the sample shall include snubbers from the following categories:

l.' The first snubber away from each reactor nozzle.

2.' Snubbers within five f eet of heavy equipment (valves, pumps, turbines, motors)

3. Snubbers connected to saf ety/ relief valve discharge piping within 10 feet of the valve.

c)

If any snubber selected for functional test either fails to lock up or f ails to move, the cause shall be evaluated and if the failure is caused by manuf acturing or design deficiency, all snubbers of the same design subject to the same 3

defect shall be functionally tested.

This testing requirement is independent of the requirements above for snubbers not meeting the functional test acceptance criteria.

d)

Snubbers which'are especially difficult to remove (as identified in Table 3.11.D.1) or are in high radiation areas during shutdown (dose greater than 100 mrem / hour) shall be included in i

the representative sample

~

except for those snubbers specifically exempted by the NRC.

kiendment No. 101 h

L PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.ll.D.5 In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next testing cycle.

If such a failed snubber was replaced, both the replacement snubber and the repaired snubber (if it had been repaired and installed in another position) shall be retested.

The test results of these snubbers may not be included for the resampling of 4.ll.D.4.a.

4.11.D.6 For snubbers found inoperable, an engineering evaluation shall be performed to determine a) mode of failure, and b) if there is any adverse effect on

~

the supported piping or components due to the snubber

/

inoperability.

1 4.ll.D.7 Hydraulic Snubbers Functional Test Criteria:

Functional test shall verify that:

l a)

Restraining action is achieved within specified range of velocity or acceleration in both compression and tension.

b)

Snubber bleed rate is i

i within the specified range in both tension and compression.

1 Snubbers specifically required not to displace under continuous load shall have this capability verified.

l Amendment No.101

-234d-

PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.ll.D.8 Mechanical Snubber i

Functional Test Criteriar Functional tests shall i-verify that:

,a)

The force that j

initiates free movement of the snubber rod in either 4

tension or compression is less than the specified maximum drag f orce.

Drag force shall not have increased more than 50%

since the last functional test.

b)

Restraining Action is achieved within the specified range of velocity or acceleration in both tension and compression.

c)

Snubber release rate, where required, is within the specified range in

{

compression or tension.

Snubbers specifically required not to displace I

under continuous load 3

shall have this capability j

verified.

4.11.D.9 Service Lif e Monitoring I

A record of the service life of each snubber i

listed in Table 3.11.D.1, the date of commencement of servi ce -life, (January 1, 1978, unless otherwise 4

i specified) and the installation and maintenance records upon which the service life is based shall be maintained.

4 2

once each operating cycle, 1

these records shall be j

reviewed to verify that no snubber service lif e shall be exceeded prior to the next revi ew.

If the service lif e will be exceeded then either recondition or replace the snubbers or re-evaluate the service life.

Am:ndment No.101 4

-234e-

s PhAP3 Unit 2 TABLE 3.11.D.1 Dals tY_E uliitLEb9GLS99ersE!9Ka_Daubbe rs).

HIGH (1)

NADIAYION AREA ESPECIALLY (1)

INACCESSIBLE (1)

SNudBdk SYSTh.K DuhtNG DIFFICULY DURING HONMAL sudeiH L UCA H Dii _MQ__ELEvlI19il atiE99his TQ_RIt0YE

_._QEMBM10G TXELUL__.

See 4.11.D.4.d.

1-GG-S-1 MSRV Drywell 135 Y

Y H

1-GG-S-2 HSEV Drywell 135 Y

Y H

1-GG-S-3 tiSR W Drywall 135 Y

Y H

1-GG-3.i M.3RV Drywell 135 Y

Y H

1-GG-S-5 MSRV Drywell 135 Y

Y ll i

1-GG-S-b MSEV br1. sell 135 Y

Y H

1-GG-S-7 EURV Drywell 135 l

Y Y

H 1-GG-S-6 t*.Sk V Drywell 135 Y

Y H

1-GG-S-5 H.iRV Drywell 135 Y

Y H

1-GG.3-10 MSRV Drywell 135 Y

Y H

1-GG-S-11 MSHV Drywell 135 Y

Y H

1-GG-S-12 MSRV Drywell 155 N

Y H

1-GG-S-13 IISRV Drywell 135 Y

Y ll 1-GG-S-14 itsnv Drywell 135 N

Y H

1-OG-S-15 hsHV Drf. sell 135 Y

Y H

Amendment No. 101

-234f-

PbAPS Unit 2 TABLE 3.11.D.1 tialstY_Balited_ Shock su22ressors _ isneedtst HIGil (1)

RADIATIDN ANEA ESPECIALLY (1)

INACCESSIBLE (1) h;406hL's SYSTEP.

DURING DIFFICULT DURING NORMAL tWOkhd

O T19d__ add ELEY&I193 dilLJIQ9tM!

19_E dQYli JERA1193 IIEE_ilL__.

See 4.11.D.4.d.

1-GG-S-16 hShv Drfwell 135 N

Y H

1-GG-S-17 tuiEV Drfwell 135 N

Y H

1-GG-S-18 t; Sky Drfwell 135 N

Y H

1-GG-3-19 MSRV Drywell 135 N

Y H

1-GG-S-20 MSRV Drywell 135 Y

Y H

I 1-GG-S-21 hSkV Drywell 135 Y

Y H

1-GG-S-22 MbRV Drywell 135 N

Y H

1-GG-S-23 MSHV Drywell 155 Y

Y H

1-GG-S-24 IISRV Drfwell 155 Y

Y H

1-GG-3-25 tis R V Drywell 155 Y

Y H

1-GG-S-26 IISHV Drfwell 155 Y

y li 1-33-S-27 MSHV Drywell 155 Y

Y H

1-GG-S-26 MSRV brfwell 155 Y

Y H

1-GG-J-29 I::2kV Drfwell 155 Y

Y H

1-GG-J-30 1 JHV ptfaall 155 Y

y Amerdment No.101

o PLAP3 Unit 2 TABLE 3 11.D.1 GaintY_Beleted snock sunntammers_lEInauharal.

HIG.1 (1)

~

RADIATION AREA ESPECIALLY (1)

IMACCESSIBLE (1)

SNUuhEE SYSTEh DUWING DIETICULT DURING I?ORMAL hys.}p.g3 L9C_3ILQd__&!iD ELEV&IlQ!(

EMUIQQtR{

IQ_BC.10VL QEEBd112ti IXE_E_,1][__

See 4 11.D.4.d.

1-GG-3-31 MSRV Drfwell 155 Y

Y H

1-GG-S-32 HSRV Drywell 155 Y

Y H

1-GG-S-3J HURV Drywell 155 Y

Y H

1-GG-S-34 HSRV Drywell 155 Y

Y H

1-GG-S-35 t:SRV Drywell 155 Y

Y H

g 1-GG-S-36 H5RV Drywall 155 Y

Y H

1-GG-S-a3 HORY prywell 155 Y

Y H

1-GG-S-o4 H5RV Drywell 155 Y

Y H

1-GG-s-65 F.URV brywell 155 Y

Y H

1-GG-S-56 bdWV Dry well 155 Y

Y H

1-GG-3-67 McRV Drywell 155 Y

Y H

1-GG-S-i,8 MSatV Drywell 155 Y

Y H

1-GG-3 u9 r.bEV prywell 155 Y

y H

1-dG-G-72 HsRV Drywell 155 Y

Y H

1-GG-3-74 f.S EV pr,well 155 Y

Y

.H Amendment flo.101

- 2 3 s:h-

e PSAPS Unit 2 TABLE 3.11.D.1

]

4.idIR$Y. EMASER1 EbSGk S'3DEIRkEQIE (83&EhlIEl.

HIGH (1) 2 RADIATIOl.

AREA EdPECIALLY (1)

INACCEJSIBLE (1)

SikihBElf SYSYa:H DURING DIFFICULT DURING N0kMAL hutidth LLEa11gn gD gLgnIlgg 3ng1999g Ig_ggagyg

__2EER&I12H TIEE_UL__.

See 4.11.D.4.d.

1-GG-S-15 hSHV Drywell 155 Y

Y H

1-GG-S-76 MShV Drywell 155 Y

~Y H

1-GG-S-77 MSRv Drywell 155 Y

Y H

1-GG-3-78 I%RV Drywell 155 Y

Y H

1-GG-S-7!r MJR*/

Drywell 155 Y

Y H

4 I

i 1-GG-S-80 MSkV Drywell 155 Y

Y H

1-JG-S-81 Makv Drywell 155 Y

Y H

1-GG-S-82 HSRV Dryuell 155 Y

Y H

1-GG-3-83 MSRV Drywell 155 7

Y H

SS-A-1 M. tin Steinen Dr,uell 155 Y

Y H

SS-A-3 Mair. Stears Drywell 155 Y

Y H

~

SS-3-1 hot s: Steiam Drywell 155 Y

Y H

SS-B-3 Hsin steam Drywell 155 Y

Y H

SS a-84 Main Steism Drywell 155 Y

Y si i

35-d-5 I:.ai n S te.cs.

Dryuell 155 Y

Y H,

Amendment No. 101

- 2 38:1-

PbhPS Unit 2 TAEsLE 3.11.D.1

~

delM1Y_E91Altilsness_ftuantessoIa_lsashhatEl HIGH (1)

RADIATIDA AREA E3FECIALLY (1)

INACCESSIBLE (1)

SNUEUEN S YS'1'th DURING DIFFICULT DURING h0RMAL tiMUHd LsNaII9el AUD LLEv_&I193 SHUID993 N_E5iER

__QEEEAII26 IIH_ht__

Sec 4.11.D.4.d.

SS-h-6 Win Stes. Dr well 155 s

Y Y

H SU-C-1 Nin Steam. Dryuell 155 Y

Y H

SS-C-3 in Ste.sas Dr well 155 s

Y Y

ti SS-C-4 Min Stoane Drywell 155 Y

Y H

I bS-C-5 i n S t e.as, Orjuell 155 Y

Y ti i

SS-C-6 thin Stesse Drjuell 155 Y

Y H

j SS-D-1 hin Steas. Drywell 155 Y

Y H

j SS-D-3 hin Steam Drywell 155 Y

Y 31 SS-1-A RECARC Crywell 120 Y

Y H

SD-1-B HECIRC Drywell 120 Y

Y H

I SS-2-A h.C1kC Laywell 130 Y

Y H

]

SS-2-a kECIEC Drywell 130 Y

Y H

SG-J-A hi.CIkC Cryuell 140 Y

y n

SS-3 a 1.LCinc crywell 140 Y

Y 11 SS-i-C hs.CInc D y Jell 140 Y

y n

4

- 2 3 8. j-Amendment No. 101 O

o PdkP5 Cnit 2 YABLE 3.11.D.1 EateLY_EclainLan9sLEueeressors (Ensuharst HIGr1 (1) 8 stADIATIOf.

AREA ESPECIALLY (1)

INACCESSIBLE (1)

SNUbbEh S YS?!.i1 DURING DIEFICULT DOAING i+0RMAL HU_UUed L 6 193 add ELEY&I19!!

Mulr1DQLM1 IQ_RX&2Mk

_2EEE&I123 IIEK_12L_

See 4.11.D.4.d.

SS-3-D kiCINC Dtyuell 140 Y

Y H

SS-5-A kiCIkC Drywell 150 Y

Y H

SS-S.s RSCIRC Cr)well 150 Y

Y H

SS-5-C h1CINC D ywell 150 Y

Y H

SS-5-D RECIEC Drywell 150 Y

Y ti t

SS-6-A hiCINC Lafuell 130 Y

Y H

SS-6.s FECIHC ctyuall 130 Y

Y H

Il-3 LS-14 2 - 1 Control kod urywell 145 N

Y M

Dtive Surely cedles t

H-JLS-142-2 Constrol Wad Drywall 145 N

Y M

Drive Supply l

Bandlus si-3La-142-3 Control 101 brguell 145 u

y n

Drive Sult.1y 1:anoic s

.-3 L-142-4 Ccetrol Rod urywell 145 N

Y n

)

t.: 1 ve ::a, a.1; L os.. ales Amendment No.101

-234k-E 4

r PSAPE Calt 2 TABLE 3.11.D.1 Egigtv Eglated snock suentassors isoqDbers)

HIGd (1)

NAtel ATID 4 AREA ESPECIALLY (1)

INACCdSSIbLE (1)

C.NuthEh SYSTcl:

DURING DIFFICULT DURING NORMAL lil!d23j{

LgCAYIO.

6N,D [L(YAI M MH01DOWtd TO idEH0VE DPEERIl2M IIEU2L.

See 4.11.D.4.d.

H-3Ls-142-5 Control sioa brywell 145 W

Y M

Drive supply but.nles li-3 LS-1

2 - 6 Control Eo.1 Drywell 145 N

Y M

Drive Sun,1f bureales C-3L3-142-7 Control Mad Drywell 145 N

Y M

Driwd SJpt.ly I

Luncles d-3 LS-18. 2 - 8 Control Rod Drywell 145 N

Y tl Drive Supply bundles 6-DD:iL-S-5 FeeJw. ster Drywell 168 Y

Y H

6-DUut.-3-6 Fedawater Drywell 168 Y

Y H

0-DOT,-d -7 Feeduater Drywell 168 Y

Y H

6-DI,HL-s-b Feeuwater Dryuell 168 Y

Y H

6-Dire t.-s-J iecowater Drywell 168 Y

Y H

o-DD..L-S-10 treawater Drywell 168 Y

Y H

6-DD4L-s-11 Fcesswa tet Drywell 155 Y

y 3:

-2341-Amendment No. 101 6

Unit 2 nme:>

TACL 3.11.D.1

~

Safety Related Shock Suppressors (Snubbers)

HIGH (1)

RADIATION AREA ESPECIALLY (1)

INACCESSIBLE (1) l SNUBBER SYSTEN DURING DIFFICULT DURING NORNAL NUMBER LOCATION AND ELEVATION SHUTDOWN TO REMOVE OPERATION TYPE (2)

See i

4.11.D.4.d.

7 i

6-DDNL-S-12 Feedwater Drywell 155 Y

Y H

j 6-DDNL-S-13 Feedwater Drywell 155 Y

Y H

[

~

6-DDNL-S-14 Feedwater Drywell 155 Y

Y H

9-MB-H51 Torus Vac. Skr.

116 N

N N

N j

9-MS-H54 Torus Vac. Skr.

116 10-HB-S-1 RNR Torus Room 93 g

N N

H l

\\

H 10-HB-S-2 RHR Torus Room 93 N

N l

10-HB-S-7 RHR B RHR Room 124 N

N d

1 l

10-HB-S-8 RNR Torus Room 93 N

N H

l l

10-GB-S-12 RHR C RHR Room 98 N

N H

4 10-GB-S-43-1 RHR Torus Room 130 Y

N H

t 4

10-GB-S-43-2 RHR Torus Room 130 Y

N H

j 10-GB-S-44 RHR Torus Room 128 Y

N H

10-GB-S-48 RHR R RHR poom 124 N

N H

i 10-CB-S-49 RHR B RHR Room 124 N

N H

kl 10-GB-S-50 RHR B RHR Room 98 N

N i

)

10-rst-S-51 RIIR C RIIR Room 98 N

N H

Amendment flo.101

-2%m-

=

~

i PDAPS Url t.

2 TABL2 3.11.D.1 OdfillY_Bglgtgd Shocit Su29Gft!9H_M99h9tGl HIGH (1)

RADIATION AREA ESPECIALL*J (1)

INACCESilBLE (1)

Si4Ubd';N SYSTr21 DURINJ DIFFICULT DJdING NORMAL hMdutB LGH9 f__N._!D ELEY&Il91 EdgIQQt!!!

IQ_ggy_YE

_QEEB8HQlf HEE _M L__

See 4.11.D.4.d.

10-Gd-S-Se Eis C kiiR Roca 124 N

N H

10-GM-3-53 Elid C Rilk Roos.

124 N

N H

10-GB-S-54 R!!E Torus Room 130 Y

N H

13-Gu-S-55 Erik 1orus Roosa 130 Y

N H

10-Ju-S-58 EliR H Ella Rooes 98 N

N H

I 10-JC4-S-73 khk Dry.4 ell 180 Y

Y H

10-Ders-S-74 kils Drywell 180 Y

Y H

10-Gai-3-7 7 k*ilF A Et:R Room 102 N

N M

10-Gs-S-lo halk A 'dia Roota 102 N

N M

10-Ges-S-75 kHR A bliR Roosa 93 N

N M

10-Gb-S-80 WhR D hsiR Rocan 102 N

N M

10-Gh-S-79 kuk D EhR Roose 102 N

N M

10-bu-S-73 kmi D Elik Roo.a 93 N

N H

10-Gb-S-51 k.th S h!!k Rcom 120.5 14 N

M 13-GL-S-92 ha.h C b.IE Wooc.

120.5 N

N M

Amendment No. 101

-23 am-l

UnAL 2 TAE..

3.ll.D.1 Safety Related Shock Suppressors (Snubbers)

HIGH (1)

RADIATION AREA ESPECIALLY (1)

INACCESSIBLE (1)

SNUBBER SYSTEM DURING DIFFICULT DURING HORMAL NUMBER IDCATION AND ELEVATION SHUTDONN TO REMOVE OPERATION TYPE (2)

See 4.11.D.4.d.

12-DCN-S-2 RNCU Iso. Valve Rm 173.5

Y N

H 12-DCN-S-5 RNCU Drywell 165 Y

Y H

12-DCN-S-7 RNCU Drywell 165 Y

Y H

12-DCN-S-8A RNCU Drywell 165 N

Y M

14-DCN-S-23 Core Spray Drywell 168 Y

Y H

14-DCN-S-24 Core Spray Drywell 168 Y

Y H

14-DCN-S-26 Core Spray *Drywell 168 Y

Y H

14-DCN-S-27 Core Spray Drywell 168 Y

Y H

l 13-HB-S-1 BCIC RCIC Room 107 Y

N H

13-DDN-S-13 BCIC RCIC ROOM 96 N

N H

13-MB-S-14 BCIC RCIC Room 102 Y

N H

13-DBN-S-15 RCIC RCIC Room 107 Y

N H

~

13-DBN-S-16 BCIC Torus Room 140 Y

N H

23-DBN-S-1 HPCI HPCI Room 112 Y

Y H

23-DBN-S-2 HPCI HPCI Room 112 Y

N H

Amendment No. 101

-2%o-e e

l PBAPS Unit. 2 TABLR 3.11.D.1

~

Ediety Belited Shock Suppressors Isnmenits).

HIGH (1)

RADIATIOt:

AREA ESFECIALLY (1)

INACCESSIBLE (1)

EMUddEb SYSTD1 DURING DIFFICULT DtHtirIG EORMAL p 3Es L!K a n c:.

A'4D ELEvartgs squiggga Ig_EEHovh

__2EERG123 HEE _Un see 4.11.D.4.d.

23-DbM-4-3 HKI I;PCI hoot 97 N

13 H

23-DbM-3-4 hKI HPCI E m -

97 N

N H

23-DO.4-3-9 HPCI asPCI Room 105 Y

W H

23-db-5-16 MeTI HPCI koom 103 N

14 H

23-188-S-19 HPCI liPCI Rooss 103 Y

N

'N 2 3 -DM 2 2 HFCI Drywell 155 Y

Y H

l 23-Db:1-s-23 HPCI Drywell 155 Y

Y H

23-DDN-s-25 HFCI hPCI kcoar 105 Y

~ H H

(

23-DbH-3-27 HPCI MPCI koon.

112

=

y W

H 23Dadi-s-28 hPCI Turus Room 117 Y

N H

~

23-DdN-3-2*>

hKI Torus Eoor 117 Y

N H

23-DDN-3-35 Mir!

Torus Ecos.

120 N

N M

2 3 -itu-4-30 FIFCI dPCI Rom 93 N

N H

L l

2 3 -ilh-S-3 6 IIFCI sii'CI ktx,c 103

.4 N

1:

l l

2 3 - 1118 3 1 1:aCI JN1 koo:a 103

4 N

H Amendment No. 101

-23=p-,

I

~

. -~.

PBAPS Ccit 2 TABLE 3.11.D.1

~~

Safety.Fe1.ited shock so nressors Isnuoners)

HIGd (1) aADIATIos AREA ESPECIALLY (l)

INACCESSIBLE (1)

SNUESul:R SY3?i11 DUdING DIEFICULT DJRING HOkHAL i

ItMtlksd LL M 105 AUQ__fdKvR98 Sums ro d qt-

_ 3 PEF 41328 HEE _HL_

see 4.11.D.4.d.

2 3-Hii-S-3 4 HFCI

'Iorus koom 126 Y

N N

l

~

21-itc-3-55 HP: 1

'Iorus doom 126 N

N M

L 1-GG-S-101-A MSEv Drywcil 135 Y

Y M

1-sG-3-101-3 HsEV Drfwell 135 Y

Y M

1 -GG-S-10 2 -;. t'.SE V Drywell 135 Y

Y ti I

6 Y

Y M

1-GG-3-102-a HSaw Drfwell 135 1-GG-S-103-A r.sEV Drypell 135 Y

Y M

1-GG-S-103-8 in,RV Drywell 135 Y

Y M

1 -GG-S-104-A t.SEV Drywell 135 Y

Y M

1-GG-s-1Go-a triav Driuc11 135 Y

Y M

1-GG-S-105-A tisav Drywela 135 Y

Y M

i 1-GG-3-105-d t sky ist ywell 135 Y

Y H

1-GG-S-10s-A FIEV Dryuell 135 Y

Y H

i 1-GG-S-10s-u r.nav Drfuell 135 y

y g

i 1-GG-s-106-h t.Juv Drywell 145 Y

y n

Amendment tio.101

-23ag-1

OlsA L 4 TABL. J.ll.D.1 y

Safety Related Shock Suppressors (Snubbers) g HIGH (1) g RADIATION AREA ESPECIALLY (1)

INACCESSIBLE (1) g SNUBBER SYSTEM DURING DIFFICULT DURING NORMAL NUMBER IDCATION AND ELEVATION SHUTDONW TO REMOVE OPERATION TYPE (2)

E See 4.11.D.4.d.

1-GG-S-108-B MSRV Drywell 145 Y

Y M

l-GG-S-109-A MSRV Drywell 145 Y

Y M

1-GG-S-109-B MSRV Drywell 145 Y

Y M

1-GG-S-110-A MSRV Drywell 145 Y

Y M

1-GG-S-110-B MSRV Drywell 145 Y

Y M

l-GG-S-Ill-A MSRV Drywell 145 Y

Y M

1-GG-S-Ill-B MSRV Drywell 145 Y

Y M

1-GG-S-ll2-A MSRV Drywell 145 Y

Y M

1-GG-S-ll2-B MSRV Drywell 145 Y

Y M

l-GG-S201 MSRV Drywell 160 Y

Y M

1-GG-S202 MSRV Drywell 160 Y

Y M

l-GG-S203-A MSRV Drywell 160 Y

y M

l-GG-S203-B MSRV Drywell 160 Y

Y M

~

1-GG-S204-A MSRV Drywell 130 Y

Y M

l-CG-S204-B MSRV Drywell 130 Y

Y M

l-GG-S205-A MSRV Drywell 160 Y

Y M

1-GG-S 20 5-B MSRV Drywell 160 Y

Y M

1-GG-S206-A MSRV Drywell 160 Y

Y M

u..

TABL 3.ll.D.1 P"fcty Relrted Chock Suppressorn (Snubbera)

HIGH (1)

RADIATION AREA ESPECIALLY (1)

IMACCESSIBLE (1)

SNUBBER SYSTEM DURING DIFFICULT DURING NOIWGAL MUMBER IACATION AND ELEVATION SHUTDONN TO REMOVE OPERATION TYPE (2)

See 4.11.D.4.d.

1-GG-S206-B MSRV Drywell 160 Y

Y M

l-GG-S207-A MSRV Drywell 125 Y

Y M

l-GG-S207-B MSRV Drywell 125 Y

Y M

1-GG-5208-A MSRV Drywell 125 Y

Y M

l-GG-S208-B MSRV Drywell 125 Y

Y M

l-GG-S209-A MSRV Drywell 125 Y

Y M

i 1-GG-5209-B MSRV Drywell 125 Y

Y M

Notes for Table 3.11.D.1 1)

Yes (Y) or Mo (N) 2)

Hydraulic (B) or Mechanical (M) kzendment r:o.101

-231e-4

4 1

1 PsAPS I

3.11 BASES i

j Alternate Heat Sink 1

The alterna}te heat sink is provided as an alternate source of i

I cooling water to the plants in the unlikely event of loss of the normal heat sink (Conowingo Pond) or the maximum credible l

flood.

Por the condition of loss of the normal heat sink, l

z the contained volume of water (approximately 3.7 million gallons, which corresponds to a gauge reading of 17')

4 provides a minimum of seven days cooling water to both plants p

for decay heat removal.

The operability requirements for the i

alternate heat sink are specified in Specification 3.9.

I i

l C.

Emereeney Shutdown Control Panels 1

l

}

The Emergency shutdown Control Panels are provided to assure the capability of taking the plants to the hot shutdown i

j condition external to the control room for the unlikely condition that the control room becomes uninhabitable.

I J

j D.

Shock Suporessors (Snubbers) on Safety Related Systems 4

Snubbers are designed to prevent unrestrained pipe motion i

i under dynamic loads as might occur during an earthquake or i

severe transient while allowing normal thermal motion during startup and shutdown.

The consequence of an inoperable

{

t snubber is an increase in the probability of structural damage to piping as a result of seismic or other event j

i

}

initiating dynamic loads.

It is therefore required that all 1

snubbers necessary to protect the primary coolant system or j

any other safety system or components be operable during j

reactor operation.

j Secause the snubber protection is required only during low i

1 probability events a pers.od of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is allowed for repairs or replacements.

A determined effort will be made to i

}

repair the snubber as soon as possible.

This allowable i

repair period is consistent with the allowable repair items s

i of other safety related components such as RER pumps, EPCI subsystems, ADS valves and diesel generators.

1 An engineering analysis must be performed on supported 4

I components when a snubber is determined to be inoperable.

The purpose of this analysis is to assure that the supported components have not been damaged as a result of the snubber inoperability.

l i

l Amendment No. 101

- 235a -

i

__._,._- --,,- _ _--..m

_._m.

b 4

l pSAPs I

[

i 4.11.

BASES l

B.

Alternate Meat sink Facility No surveillance requirement other than a monthly level check is expressed for the alternate heat sink since the associated i

equipment surveillance testing is conducted as required by l

d specification 3.9.

t C.

Emergency shutdown-Control Panels I

'l I

once per week verification of the panels being properly secured is considered adequate.

The associated equipment is i

proven operable during surveillance testing of that equiument.

An operability verification by electrical test at 1

each refueling outage is adequate to assure that the panels i

are avellable and een perform their design function.

j D.

shock suporessors (snubbers) on safety Related systems I

r All safety related snobbers are visually inspected to verify,

1) proper orientation, 2) freedom of movement where possibig to induce motion manually without disconnecting the enubber, j

3) proper attachment to structures and equipment, and 4) proper hydraulic fluid level for hydraulie enubbers.

];

anubbers are eategorised into two groups, "aesessible" or

" inaccessible", based on their aseessibility for inspection

{

during reactor operation and drywell inertment.

The required' inspection interval varies inversely with the observed snubber f ailures.

The number of inoperable enubbers found i

j during a required inspection determines the time interval for 2

i the next required inspection.

Inspectione performed before l

that interval has elapsed may be used as a new reference i

point to determine the next nnspection.

However, the results of such early inspections will only be used to shorten the

{

required interval and not to lengthen it.

I I

r when the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other

)

enubbers that may be generion11y susceptible, and verified by j

inservios functional testing, that snubber may be exempted from being counted as inoperable.

Generion11y sueoeptible j

snubbers are those which are of a specific make or model and j

l have the same design features directly related to rejection of the snubber by visual inspection or are similarly loosted or exposed to the same environmental conditione such as temperature, radiation, and vibration.

When a snubber le found inoperable an engineering evaluation is performed to determine a) enubber mode of failure and, b) if there is any adverse ef f ect or degradation on the supported piping or equipment due to the f ailure.

1 To f urther ineresse the assurance of snubber reliability, f unctional tests will be performed once each operating cycle.

4 Amendment No. 101

- 235a -

i t

,.,,.,.na,..-.,,w,mn

,,n.,,-,

,,,,n,~.,

._,_,,,_,__,.,-n,.,,_n,_._

e,

PBAPS Ten percent of each type (hydraulic or mechanical) of snubber J

on each unit shall constitute an adequate sample.

t Nigh radiation areas (as defined in CFR 10 Part 20.202) means any area, (ccessible to personnel, in which there exists radiation at such levels that a major portion of the body

(

could receive, in any one hour, a dose in excess of 100

.c millires.

Snubbers considered especially difficult to remove (as indicated in Table 3.11.D.1) are those which because of 1

size, weight, or geometry of installation require the use of unusual rigging equipment or arrangements for their removal, j

or require more than three hours of effort in their removal.

l The service life of a snubber is monitored to assure that consideration is taken for the age of the expendable 1

components.

The service life is based upon manufacturer's recommendation, service conditions, maintenance history, operating esperience and test and inspection results.

When the review of service life records reveals that a snubber is i

nearing the end of its design service life, efforts are made j

to include that snubber in the next functional test cycle or the service life is reevaluated.

The purpose of the 1

reevaluation is to extend the service life based upon i

experience and information gained during operations.

The i

results of functional testing and inspection may be used to i

alter the service lives of all snubbers of similar design 4

j operating under similar conditions.

i i

I i

i l

4 I

l l

l i

l 1

i i

l t

e i

Amendment No. 101 234b.

g** "%,y e

o UNITED STATES

[ "*g

'h NUCLEAR REOULATORY COMMISSION

.,Q WASHINGTON. O C. 20SSS PHILADELPHIA ELECTRIC COMPANY PUBLIC 5ERVICE ELECTRIC AND GA5 COMPANY DELMARVA POWER AND LIGHT COMPANY ATL ANTIC CITY ELECTRIC CUMPA%*

00CKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSF.

Amendment No.103 License No. OPR 56 1.

The Nuclear Regulatory Connission (the Conmission) has found that:

A.

The application for amendment by Philadelphia Electric.ompany, et c

al.(thelicensee)datedMarch 24, 1981, as supplemented by letters dated August 6, 1981, December 13, 1982. June 27. 1983, September 14, 1983, and January 26, 1984, comp 1tes with the standards and requirements of-the Atomic (norgy Act of 1954, as amended (the Act), and the Conmission's ruler and regulations set forth in 10 CFR Chapter 11 B.

The facility will operate in conformity with the application, the provisions of tio Act, and the rules and rngulations of the Connission s C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted withcut endangering the health and safetyofthepublic,and(11)thatsuchactivitieswillbeconducted in compitance with the Conmission's regulationst D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the publict and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this Itcense amendant, andparagraph2.C.(2)ofFacilityOperating1.icenseNo.OPR5615hereby amended to redo as followst

2 Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.103, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.

3.

This Itcense amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

}l;y is /\\ d'he fr* of George'W Rivenbark. Acting Chief Operating Reactors Branch No. 4 Division of Licensing Attachment Changes to the Technical Specifications Date of Issuance July 2, 1984 C

l

j

=

)

ATTACHMENT TO LICENSE AMENDMENT N0. 103 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of charige.

Remove Insert 234a 234a 234b 234b 234c 234c 234d 234d 234e 234e 234f 234f 234g 234g 234h 234h 234i 2341 234j 234j 234k

-- 234k 2341 2341 234m 234m 234n 234n 234o 234p 234q 234r 234s 235a 235a 236a 236a 236b 236b

-k I

t I

i

PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11.D. Shock Suppressors 4.ll.D. Shock Suppressors (Snubbers) on Safety Related (Snubbers) on Safety Related Systems Systems 3.ll.D.1 During all modes 4.ll.D.1 of operation all e snubbers listed in Table Snubbers listed in Table 3.11.D.1 shall be operable 3.11.D.1 shall be demonstrated except as noted in.

' OPERABLE by performance 3.11.D.2 and 3.11.D.3 of the following augmented below.

inservice inspection program 4

and the requirements of Specification 4.6.G.

3.ll.D.2 During operation in the 4.' 11. D. 2 cold shutdown or refueling modes, snubbers located on Snubbers listed in Table system required.to be operable 3.ll.D.1 shall be visually shall be operable except inspected according to the as noted in 3.11.D 3.

folivaing schedule.

No. of Snubbers Next Visual Found Inoperable Inspection Durin'g Inspec-Period 3.11.D.3 With one or more tion Period snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , replace or restore o

la mo. + 25%

the inoperable snubber to the 1

12 me. T 25%

operable status and perform 2

6 mo. T 25%

an engineering evaluation per 3,4 4 me. T 25%

specification 4.11.D.6.

If 5,6,7 2 mo. T 25%

these requirements cannot be 8 or more 1 me. + 25%

met, declare the supported system inoperable and follow the applicable Limiting The recuired inspection Condition for operation for interval shall not be that System.

lengthened more than one step at a time.

The provisions for extending surveillance frequency included in Section 1.0 Defini-tions do not apply.

Snubbers may be categorized in two grouns,

" accessible" or " inaccessible",

i based on their accessibility for inspection during reactor operation. These two groups may be inspected independently according to the above schedule.

4 I

Amendment No. J/, //, 86,1C3

. -. =

PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11.D.4 Snubbers may be 4.11.D.3 added to saf ety related systems without prior The visual inspection License Amendment to shall verify that 1) there are Table 3.ll.D.1 no indications of damage or l

provided that a impaired operability, 2) attach-revision on Table ments are secure, and 3) there 3.11.D.1 is included is freedom of movement with the next License if this can be verified Amendment request.

without disconnecting the snubber.

Snubbers which appear to be inoperable may be made operable for the purpose of establishing the next visual inspection interval, providing that 1) the cause of the rejection ~ is clearly established and remedied for that particular snubber and for other generically susceptable snubbers; and 2) the aff ected snubber is functionally tested in the as found condition and determined operable per Specification 4.ll.D.7 or

- 4.11.D.8, as applicable. When the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined to be inoperable for the purpose of establishing the next visual inspection interval.

4.11.D.4 Functional Test

. a) Once each operating cycle, during shutdown, a representative sample of 10% of each type of (mechanical or i

l hydraulic) snubber shall be functionally tested either in place or in a bench test.

For every unit found to be t

l inoperable an additional 10% of i

that type of snubber shall be j

functionally tested until no more failures are found or all l

snubbers of that type have been tested.

The f unctional test re quirement for mechanical snubbers will not take effect Am:nchent No. 103

-23.4b-

PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS until the first refueling outage commencing one year after approval, by the NRC, of this Technical Specification amendment.

b) The representative sample selected for functional testing shall include various configurations, operating environments, sizes, and capacities of snubbers.

At least 25% of the sample shall include snubbers from the following categories:

l. The first snubber away from each reactor nozzle.

2. Snubbers within five f eet of heavy equipment (valves, pumps, turbines, motors)

3. Snubbers connected to saf ety/ relief valve discharge piping within 10 feet of the valve.

c)

If any snubber selected for functional test either fails to lock up or f ails to move, the cause shall be evaluated and if the failure is caused by manufacturing or design deficiency, all snubbers of the same design subject to the same defect shall be functionally test ed.

This testing requirement is independent of the requirements above for snubbers not meeting the functional test acceptance criteria.

d)

Snubbers which'are especially difficult to remove (as identified in Table 3.11.D.1) or are in high radiation areas during shutdown (dose greater than 100 i

mrem / hour) shall be included in the representative sample except-for those snubbers specifically exempted by the NRC.

Mirndment No.103

-234c

~

i PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS e

J 4.11.D.5 In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next testing cycle.

If such a failed snubber was replaced, both the replacement snubber and the repaired snubber (if it had.been repaired and installed in another position) shall be retested.

The test results of these snubbers may not be included for the resampling of 4.11.D.4.a.

4.11.D.6 For snubbers found inoperable, an engineering evaluation shall be performed to determine a) mode of failure, and b) if there is any adverse effect on the supported piping or components due to the snubber inoperability.

4.11.D.7 Hydraulic Snubbers Functional Test Criteria:

Functional test shall verify that:

a)

Restraining action is 1

achieved within specified range of velocity or acceleration in i

both compression and tension.

b)

Snubber bleed rate is within the specified range in l

both tension and compression.

Snubbers specifically required l

not to displace under t

continuous load shall have this capability verified.

1 Amendment No. 103

-234d-

7 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.11.D.8 Mechanical Snubber

~

Functional Test Criteria:

Functional tests shall verify that:

.a )

The force that initiates free movement of 1

the snubber rod in either tension or compression is less than the specified maximum drag force.

Drag force shall not have increased more than 50%

since the last f unctional test.

b)

Restraining Action is achieved within the specified range of velocity or acceleration in both tension and i

compression.

c)

Snubber release rate, where required, is within the specified range in compression or tension.

Snubbers specifically required not to displace under continuous load shall have this capability verified.

4.ll.D.9 Service Life Monitoring A record of the service life of each snubber listed in Table 3.ll.D.1, i

the date of commencement of service life, (January 1, 1978, unless otherwise specified) and the installation and i

maintenance records upon which the service life is based shall be maintained.

Once each operating cycle, these records shall be reviewed to verify that no l

snubber service lif e shall l

be exceeded prior to the next review.

If the service lif e will be exceeded then either recondition or replace the snubbers or re-evaluate the service lif e.

l Amendment No. 103

-234e-

PBAPS Unit 3 TAdLE 3.11.D.1 aaletLE21ata2_En9EiLangoressors (3090b41:21.

1 HIGH (1)

NADIATION AREA ESPECIALLY (1)

INACCESSIBLE (1)

SNUhuSR SYSTEM DUHING DIFFICJLT DURING bORMAL 4

H!!Lidh8 LGCAT191._&ifD _EtgY&IIQN guyIgggg Ig_RgigyL

_,_QEgBallQd TYEE_ [JL_

see 4.11.D.4.d 1-GG-S-1 H5RV Drywell 135 Y

Y H

j 1-GG-J-2 HSRV Drywell 135 Y

Y H

1-GG-d-3 MSRV Dryw611 135 Y

Y H

1-GG-S-4 hERV Drywell 135 Y

Y H

1-GG-3-5 HERV Drywell 135 Y

Y H

1-GG-3-6 M6AV br/well 135 f

Y Y

H s

1-GG-S-7 VARV Drywell 135 Y

Y H

1-GG-S-8 HSRV Drywell 135 Y

Y H

1-GG-S-9 HSRV Drywell 135 Y

y n

i 1-GG-3-10 HSHV orywell 135 Y

Y H

1-GG-3-11 HSEV Drywell 135 Y

Y H

1-GG-3-12 NSHV Drywell 135 H

Y H

i 1-JG-d-13 hCHV Drywell 135 Y

Y H

1-GG-3-184 MSHV prywell 135 y

y n

1-GG-3-15 MURV urywell 135 Y

y n

-234[-

Amendment No. 103 i

PEAPS Unit 3 t

TAuLt 3.11.D.1 amictr_Es16stLabest suporessora_.fannhthiral HIGH (1)

RADIATION AHEA ESPECIALLY (1)

INACCESSIBLE (1)

CNUDBr N StSTEM DURII:G DIFFICULT DOHING NORMAL tiutidH L9G119N &!!D__ELEY&IIQti allWIQ9d3 I9_ ext 19YE 3PEph11Qti IIEg_jjt_,

See 4.11.C.4.d N

Y H

1-GG-S-16 HSRV Drywell 135 1-GG-S-17 1;SRV Drywell 135 N

Y H

1-GG-S-18_

MSEV Drywell 135 N

Y H

1-GG-3-19 HSHV Drfwell 135 N

Y H

1-GG-S-20 hSRV Drywell 135 Y

Y H

4 I

Y Y

I:

1 -GG -S-21 alskV Drywall 135 4

1-GG-S-22 HSHV brywell 135 N

Y H

1-GG-S-23 hGNV Drfwell 155 Y

Y H

i 1-GG-S-24 HShv Drywell 155 Y

Y H

1-GG-S-25 Hnky Drfwall 155 Y

Y H

l 1 -GG-S - 2 6 MSHV Drywell 155 Y

Y H

l 1-GG-S-27 hSHV Drywell 155 Y

Y H

j 1-GG-S-28 t;URV Drywell 155 Y

Y H

1 -GG.5-2 9 n:.HV Drywell 155 Y

Y H

Y y

g; 1-GG-3-30 HShv Drjwell 155

~

-2348-Amendment No. 103 i

l l

i

r5APS 0014 5

YABL 3.11.D.1 Safety Related Shock Suppressors (Saubbers)

NICH (1)

RADIATION AREA ESPECIALLY (1)

INACCESSISLE (1)

SNUBBER SYSTEM DURINC DIFFICULT DURING NORMAL NUMBER LOCATION AND ELEVATION SHUTDOWN TO REMOVE OPERATION TYPE (2) i See l

4.11.D.4.d.

1-CC-S-31 MSRV Drywell 155 Y

Y M

1-CC-5-32 MSRV Dryve11 155 Y

Y H

1-CC-5-33 MSRV Drywell 155 Y

Y N

1-CC-5-34 MSRV Drywell 155 Y

Y u

1-CC-5-35 MSRV Drywell 155 Y

Y H

1-SC-5-36 MSRV Dryve11 155 I

Y Y

R 1-CC-S-49 MSRV Drywell 155 Y

Y R

j i

1-CC-5-50 MSRV Drywell 155 Y

Y M

1-GC-S-51 MSRV Drywell 155 Y

Y u

l-CC-S-52 MSRV Drywell 155 Y

Y H

i 1-CC-S-53 MSRV Drywell 155 Y:

Y H

1-CC-S-54 MSRV Drywell 155

.Y Y

H l

1-CC-S-55 MSRV Drywell 155 Y

Y H

l t

l Amendment No. 103

-234-(

)

I i

PSAPS-Unit 3

.I TABLE 3.11.D.1 -

Safety Related Shock Suppressors (Sembbers)

HICH (1)

RADIATION

~

AREA ESPECIALLY (1)

INACCESSIBLE (1) l SOUSBER SYSTEM DURING DIFFICULY DURINC NORMAL NUMBER LOCATION AND ELEVATION SNUTDOWN TO REMOVE

. 0PERATION TYPE (2 )

See 4.11.D.4.d.

i i

1-CC-8-57' HSRV Drywell 155 Y

Y E

I 1-CC-3-59 MSRV Brywell 155 Y

Y E

1-CC-8-60 MSRV Drywell 155 Y

Y M

~

1-CC-8-61 MSRV Drywell 155 Y

Y M

1-CC-S-62 MSRV Drywell 155 Y

Y M

I 1-CC-5-63 MSRV Drywell 155 Y

Y N

1-CC-5-64 MSRV Drywell 155 Y

Y H

1-CC-S-65 MSRV Drywell 155 Y

Y H

1-CC-5-66 MS RV.

Drywell 155 Y

Y H

i 1-CC-S-67 MSRV Drywell 155 Y

Y H

i

)

1-CC-s-68 HSRV Drywell 155 Y'

Y H

i 1-CC-5-69 MSRV Drywell 155 Y

Y H

I SS-A-1 Main Steen Drywell 150 Y

Y H

j SS-A-3 Main Steam Drywell 150 Y

Y H

Amendment No. 103

-2%i-i I

a

1 PbAPS Unit 3 TABLE 3.11.D.1' Saistr_Beleted_Shos!Lausatstanza_.lacubbatal.

dIGH (1)

RADIATION AREA EdPECIALLY (1)

INACCESSIdLE (1)

SildliUEk S YST E.1 DUNING DIFFICULT DURING IORMAL

__Qgggg11Qc!

TYRE _MI UHi. hhi!

In&IlDN AND ELgygl{g[{

ggjg1QQgj((

Ig_gggggyg 1

See 4.11.D.4.d SS-B-1 Main Steam Drywell 150 Y

Y H

~

SS-a-3 Main Ste.m Drywell 150 Y

Y H

ds-B-4 Main Steara Drywell 150 Y

Y H

SS-B-5 Main Steata Drywell 150 Y

Y H

SS -is-6 hain Steam Drywell 150 Y

Y H

i 5S-C-1 Main Stear.s Drywell 150 Y

Y H

ES-C-3 Hain Steam Drywell 150 Y

Y H

ES-C-4 Main Steam Drywell 150 Y

.Y H

SS-C-5 Malte Staase Drywall 150 Y

Y H

j SS-C-6 Main Ste.nm Drywell 150 Y

Y H

SS-D-1 Main Steata Drywell 150 Y

Y H

SS-D-3 Main Stei.a.

Drfuell 150 Y

Y H

SS-1-A EECIRC Crywell 120 Y

Y H

SS-1-1:

hi: CIRC Crywell 120 Y

Y H

SS-2-A RECIRC Urywell 130 Y

Y H

-234J-Amendment No.103 i

)

i I

PCAPS Unit 3 TABLE 3 11.D.1 EsittY_f!916tte_EnesiL.funersaaeta_Jansketral HIGH (1)

NADIATION I

1 AREA ESPECIALLY (1)

INACCESSIBLE (1)

SHUilugh SiSTEH DUHING DIFFICULT DdWING NORMAL

!!M!.1EEi!

L9QdlDij__&[jD ELEY&Ilgd EllMIQQtiH IQ. REMOVE

__2ERE&IlQM TIEE_1JL__

See 4.11.D.4.d SS-2-H EECIRC Urywell 130 Y

Y H

l SS-3-A kECINC Drywell 140 Y

Y H

i SS-3-8 NECIWC Dtyuell 140 Y

Y H

SS-3-C hECIRC Urywell 140 Y

Y H

l SS-3-D RECIRC Drywell 140 Y

Y H

SS-5-A Es. CIRC Urywell 150 I

Y Y

H i

JS-5-u RECIRC Dry. sell 150 Y

Y H

SS-5-C RI:.C1HC Cry. sell,

150 Y

Y H.

SS-5-D REC 1RC Drywell 150 Y

Y H

l SS-6-A REC 1hc Drywell 130 Y

Y H

SS-6-8 RECIRC Crywell 130 Y

Y H

i H-3LS-142-1 Control pod Drywell 145 N

Y H

Drive Su;tely Bandles H-3LS-142-2 cont.rol Hod Drywell 145 N

Y H

brive Sagt,1y sun.Iles l

Amendment No. 103

- 2 3 4 k-

]

PhAPS Unit 3 TABLE 3.11.D.1 SelftY_B21ditEL Snock SgapIRS40r5. ISil9hthlM1.

HIGil (1)

RADIATION AREA ESPECIALLY (1)

INACCESaleLE (1) 314U! aller SYSfDi DURING DIFFICULT DudlNG NORMAL

!! wha L9CnI191!__MD__LLEE6I19!!

timrIQ91!!i IQ_EX MYt

__DEEE&I193 IIEE_Ilt__

See as.11.p.g.d ll-3LS-142-3 Control had Drywell 145 N

Y M

Drive Supply busiales H-JLS-142-4 Control had Drfuell 145 N

Y M

Drive Sug.plf hundles h-3LS-142-S Control Eod Drywell 145 N

Y

'M Drive Surply Bunales l

li-JLS-142-6 Control food Drywell 145 N

Y M

Drive Supply dunales H-3LS-142-7 Control Mod brywell 145 N

Y M

Drive Supply Bundles.

H-3LS-142-8 Control Fod Drywell 145 N

Y H

Drive sus ply 1sundles 6-DDi L-3-5 Feeawater Drywell 168 Y

y n

6-lJDNn-3-6 Fere s.#ater Drywell 168 y

y y

6 -DD;Ju-S-7 Fs.eilw.i ter Drywell 168 Y

y n

-2341-Amendment No. 103 4

i

. es.ws Unit 3 TARLR 3.11.D.1 9afety Related Shock Suppressors (Snubbers)

HIGH (1)

ADIATION AREA ESPECIALLY (1)

INACCESSIRLE (1)

SNt1RRER SYSTEM DURTNG DT FFICULT DURING NORHAL MINRER LOCATION AND ELEVATION SHtf?DOW TO REMOVE OPERATION YYPE (2)

See 4.11.D.4.d.

6-DDNL-S-8 Feedwater Drywell 168 Y

Y H

6-DDNL-S-9 Feedwater Drywell 16R Y

Y H

6-DDNL-S-10 Feedwater Drywell 168 Y

Y H

6-DDHL-S-11 Feedwater Drywell 155 Y

Y H

6-DDNL-S-12 Feedwater Drywell 155 Y

Y H

6-DDNL-S-13 Feedwater Drywell 155 Y

Y H

6-DD4L-S-14 Feedwater Drvwell 155 Y

Y H

9-H8-H51 Torus Vac. Rkr.

116 N

N M

4-HR-H53 Torus vac. Rkr.

116 N

N M

10-HR-S-1 RHR Torus Room 95 N

N M

l ID-HR-S-7 PHR R RMR Room 124 N

N H

ID-HR-S-R PHR Torus Poom 95 N

N M

l ID-GR-S-12 PHR C RHR Room 99 Y

N H

l IO-GR-S-43-1 RHP Torus #oom 130 Y

N H

ID-GR-S-43-2 RHR Torus Room 130 Y

N H.

ID-GR-S-44 RHR Torus Room 12R Y

N H

-234m-Amendment Nc. 103 s

J PEAP3 Unit 3 TABLE 3.11.D.1 S&l21Y HMldLRG Et19GlLE9E9EdE29Is f309QDRIEl HI Gil (1)

~

HADIATIol; AREA ESPECIALLY (1)

INACCE3SISLE. (1)

Staunuds SYSTEN DUNING DItTICUL1-DdNING NORMAL HMUEE!!

in9CallCd &HD ELEE& TION DUMIQQE36 IM_EEEQYl M E E & I l 9ti IXEE_Ilt_.

see sa.1 1. D. 4. d 10 -Gd-S -Ulf NhH b RilR Hoosa 124 Il N

h 10-Gb-S-49 kHR L RelH Huom 124 N

N H

10-Gs-S-50 RaiR E kHR Roorr.

98 N

N H

10-Gd-S-51 kliR C RhN Roone 9S N

N M

j 10-G3-5-52 astR C NHR Rooms 124 N

N H

10-GB-3-53 kHR C RHR koom 124 tl N

H l

10-GB-S-54 RitR Torus Hoom 130 Y

N H

j 10-GH-5-55 heir

'Iorus Room 130 Y

N H

10-GB-S-58 kiin L hi!R Room 93 N

N H

10-Gb-S-62 RhR A RiiR Room 102 N

11 M

10-GB-3-63 klik A RilR Eoom 102 N

N M

10-GH-3-64 R!IR A EllH Hoo n 93 il N

M 30-GS-S-65 H.lR D EllR Room 102 N

N M

10 -Gil-S -o 6 hhR L. Hiih Roon 102 N

N N

10-GB-S-67 hl.H D klik Hoom 93 N

N t;

Amendment No. 103

~

i 4

4

FDAFS Unit 3 TABL. 3.11.D.1 Safety Related Shock Suppressors (Saubbers)

NICH (1) i RADIATION AREA ESPECIALLY (1)

INACCESSIBLE (1)

SCUBBER SYSTEM DURING DIFFICULT DURING NORMAL CUNBER LOCATION AND ELEVATION SNUTDOWN TO RENOVE OPERATION TYPE (2)

See 4.11.D.4.d.

10-DCN-5-73 RNR Drywell 180 N

N N

10-CCN-S-74 KNR Drywell 180 Y

Y N

10-C5-5-81 RNR R RNR Room 120 N

N 4

N 12-DCN-S-2 RUCU Iso. Valve am 173.5 Y

Y N

12-DCN-S-5 RUCU Drywell 165 Y

Y N

12-DCN-S-7 RUCU Drywell 165 l

Y Y

M i

12-DCN-S-9 RWCU Drywell 165 Y

Y M

l.

14-NCR-S-4 Core Spray B/D Core 127.5 N

N N

l Spray Room 14-DCN-S-23 Core Spray Drywell 168 Y

Y M

14-DCN-S-24 Care Fyrsy Drywell 168 Y

Y M

i 14-DCN-S-26 Core Spray Drywell 168 Y

Y H

l i

j 14-CCN-S-27 Core Spray Drywell 168 Y

Y N

{

l l

i I

l Amendment No.103

-23ho-l i

1

=

vwS Unit 3 TARr.E 3.11.D.1 Safety T'elsted Shock Supprennorn (Snubbers) i HIGH (1)

I RADTATION ARRA RSPECTAT,t.Y (1)

INACCESSIRT,R (1)

SMURP.ER SYSTEM TRJRING DIFFICULT DURING NORMAI, NtMRER lor *ATION AMD ET.EVATION SHUTDOWN TO REMOVE OPERATION TYPE (2) see 4.11.D.4.d.

i 13-MR-S-23 RCIC RCIC Room 103 Y

Y H

2 3-Dr.N-S-1 HFCI Torun Room 121 Y

Y H

7.3-HR-S-1A HPCI HPCI Room 103 Y

Y H

23-HR-S-2A HPCI HPCI Room 103 N

Y H

l 23-H9-5-3A HPCI HPCI Room 99 Y

Y H

l 1

23-DRN-S-6-1 HPCI Torus Room 121 Y

N H

{

l 23-DBN-5-6-2 MPCI Torus Room 121 Y

N H

i 23-DRN-S-22 HPCI Drywell 155 Y

Y H

23-DRM-S-23 HPCI Drywell 195 Y

Y H

23-DDN-S-29 HPCI HPCT Room 117 N

N N

23-DDN-S-33 HPCI HPCT Room 93 N

N H

i 23-DDN-S-47 HPCI Torus Room 121 N

N N

l 27-HCR-S-1R7 HPCI R/D Core 127.5 N

N N

Spray Room l

27-HCR-S-1RR HPCI Torun Room 122.R N

N M

^

-234P-Amendment No. 103 1

9 e

5 4

FSAFS Unit J YAcLE 3.11.D.1 Safety Related Shock Suppressors (Snubbers)

NIGN (1)

RADIAY10N AREA RSFECIALLY (1)

IMACCESSIRLE (1)

SNUssER SYSYEM DURING DIFFICULY DURING NORMAL

)

CUMBER LOCAYION AND ELEVAYION SHUYDOUN YO REMOVE OPERATION YYPE (2)

See 4.11. D. 4. d.

1-CC-5-101-A MSRV Drywell 135 Y

Y M

i 1-CC-5-101-5 MSRT Drywell 135 Y

Y M

1-CC-5-102-A MSRV Drywell 135 Y

Y M

E l

l 1-CC-8-102-B MSRV Drywell 135 Y

Y M

1-CC-5-103-A MSRV Drywell 135 Y

Y M

I 1-CC-S-103-8 MSRV Drywell 133 Y

Y M

1-CC-5-104-A MSRV Drywell 135 Y

Y M

f l

1-CC-5-104-R MSRT Drywell 135 Y

Y M

I 1-CC-5-105-A MSRV Drywell 135 Y

Y M

l i

{

1-CC-5-105-5 MSav Drywell 135 Y

Y M

1-CC-5-106-A MSRT Drywell 135

.Y Y

M 1-CC-5-106-3 MSRT Drywell 135 Y

Y M

i 1-CC-5-108-A MSRV Dryve11 145 Y

Y M

i 1-CC-5-100-B MSRV Drywell 145 Y

Y M

i i

a t

f

-231q-4 i

Amendment flo.103 i

l t

e

PSAFS Unit 3 l

TABLE 3.11.D.1 l

l Safety Reisted Shock Suppressors (Sembbers)

}

l MICM (1) l t

RADIAYION l

]

AREA ESPECIALLY (1)

INACCESSIBLE (1) l t-SUUBBER SYSTEM DURING DIFFICULT DURING NORMAL.

l l

_ CUMBER LOCATION AND ELEVAYION SNUYDONN TO REMOVE OPERATION YYPE (2)

?

See 4.11. D. 4. d.

I

)

1-CC-5-109-A MSRV Drywell 145 Y

Y M

i l

1-CC-5-199-5 MSRV Drywell 145 Y

Y M

1-CC-5-110-A MSav Drywell 145

.Y Y

M i

1-CC-5-110-5 MSRV Drywell 145 Y

Y M

l

~

1-CC-5-111-A MSRV Drywell 145 Y

Y M

1-0C-5-111-3 MSRV Drywell 145 l

Y Y

M f

1-CC-5-112-A MSRV Drywell 145 Y

Y M

l 1-CC-5-112-3 MSRV Drywell 145 Y

Y M

j 1-CC-5201 MSRV Drywell 160 Y

Y M

1-CC-5202 MSRV Drywell 160 Y

Y M

H l

1-CC-5203-A MSRV Drywell 160 Y

Y M

1-CC-5203-5 MSRV Drywell 160 Y

Y M

I i

1-CC-5204-A MSRV Drywell 130 Y

Y M

I 1-CC-5204-5 MSRV Drywell 130 Y

Y M

1-CC-S205-A MSRV Drywell 160 Y

Y M

-2)p-i kiendment No.103 i

i t

t i

__ = _ _ _ _ _ - -

b.4.

1 TARLE 3.11.D.1 Safctv C21oted Shock Supproccers (Cnubberc)

HT G*t (1)

RADIATION ARRA ESPECIALLY (1)

INACCESSIRLE (1)

S=RinRER SYSTEM DtIRING DIFFICULT DURING NORMAL NUMBER LOCATION AND ELEVATION SHtFrDONN

'fD REMOVE OPERATION YYPE (2) see 4.11.D.4.d.

I 1-GG-5205-R MSRV Drywell 160 Y

Y M

i l

1-OG-S206-A MSRV Drywell 160 Y

Y M

i 3

1-OG-S 206-R MSRV Drywell 160 Y

Y M

l 1

l 1-CC-5207-A MSRV Drywell 125 Y

Y M

i j

1-GG-S207-n MSRV Drywell 125 Y

Y M

i 1-GG-5 203-A MSRV Drywell 125 Y

Y M

1-GG-S209-R MSRV Drywell 125 I

Y Y

M 1-GG-S209-A MSRV Drywell 125 Y

Y M

j' 1-GG-S209-R MSRV Drywell 125 Y

Y M

14-GR-S-33 Core Spray Torum Room 128 Y

N M

t 14-GR-S-34 Core Spray Torus Roca 128 Y

N M

l j

14-MO-M-57 Core Spray Torus Room 126 Y

N M

14-Mo-S-42A core Spray Torun Room 130 Y

N M

14-MO-S-42R Core Spray Torus Room 130 Y

M l

l Notes for Table 3.11.D.1

~

1)

Yes (Y) or No (N) i l

2) flydraulic (H) n-Mechanical (M) l t;-

i Amendment No. 103

-234s-1 i

b

~

e i.

PBAPS 3.11 BASES Alternate Heat Sink The alternate heat sink is provided as an alternate source of cooling water to the plants in the unlikely event of loss of the normal heat sink (Conowingo Pond) or the maximum credible 4

flood.

For the condition of loss of the normal heat sink, the contained volume of water (approximately 3.7 million i

gallons, which corresponds to a gauge reading of 17')

provides a minimum of seven days cooling water to both plants for decay heat rsmoval.

The operability requirements for the alternate heat sink are specified in Specification 3.9.

C.

Emergenev Shutdown Control Panels The Emergency shutdown Control Panels are provided to assure the capability of taking the plants to the hot shutdown condition external to the control room for the unlikely

}

condition that the control room becomes uninhabitable.

D.

Shock Suporessors (Snubbers) on Safety Related Systems

,~

snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient while allowing normal thermal motion during i

i startup and shutdown.

The consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of seismic or other event initiating dynamic loads.

It is therefore required that all snubbers necessary to protect the primary coolant system or any other safety system or components be operable during j

reactor operation, l

Because the snubber protection is required only during low probability events a period of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is allowed for repairs or replacements.

A determined effort will be made to repair the snubber as soon as possible.

This allowable repair period is consistent with the allowable repair items j

of other safety related components such as RER pumps, EPCI subsystems, ADS valves and diesel generators.

l An engineering analysis must be performed on supported J

components when a snubber is determined to be inoperable.

The purpose of this analysis is to assure that the supported components have not been damaged as a result of the snubber inoperability.

Amendment No.103

- 235a -

PBAPS 4.11.

BASES B.

Alternate Heat Sink Facility No surveillance requirement other than a monthly level check is expressed for the alternate heat sink since the associated equipment surveillance testing is conducted as required by Specification 3.9.

C.

Emergency Shutdown-Control Panels i

once per week verification of the panels being properly secured is considered adequate.

The associated equipment is proven operable during surveillance testing of that equipm ent.

An operability verification by electrical test at each refueling outage is adequate to assure that the panels are available and can perform their design function.

D.

Shock Suporessors (Snubbers) on Safety Related Systems All safety related snubbers are visually inspected to verify,

1) proper orientation, 2) freedom of movement where possible to induce motion manually without disconnecting the snubber,

3) proper attachment to structures and equipment, and 4) 1 proper hydraulic fluid level for hydraulic snubbers.

l Snubbers are categorized into two groups, " accessible" or

" inaccessible", based on their accessibility for inspection i

during reactor operation and drywell inertzent.

The required inspection interval varies inversely with the observed snubber f ailures.

The number of inoperable snubbers found I

during a required inspection determines the time interval for j

the next required inspection.

Inspections performed before i

that interval has elapsed may be used as a new reference i

point to determine the next inspection.

However, the.results j

of such early inspections will only be used to shorten the j

required interval and not to lengthen it.

when the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted 3

from being counted as inoperable.

Generically susceptible snubbers are those which are of a soecific make or model and i

l have the same design features directly related to rejection of the snubber by visual inspection or are similarly located or exposed to the same environmental conditions such as i

temperature, radiation, and vibration.

When a snubber is found inoperable an engineering evaluation is performed to determine a) snubber mode of failure and, b) if there is any adverse effect or degradation on the supported piping or eauipment due to the f ailure.

To f urther increase the assurance of snubber reliability, f unctional tests will be performed once each operating cycle.

~

~

Amendment No. 103

PBAPS Ten percent of each type (hydraulic or mechanical) of snubberi on each unit shall constitute an adequate sample.

~

High radiation areas (as defined in CFR 10 Part 20.202) means any area, accessible to personnel, in which there exists radiation at such levels that a major portion of the body could receive, in any one hour, a dose in excess of 100 millirem.

Snubbers considered especially difficult to remove (as indicated in Table 3.11.D.1) are those which because of size, weight, or geometry of installation require the use of unusual rigging equipment or arrangements for their removal, or require more than three hours of effort in their removal.

The service life of a snubber is monitored to assure that consideration is taken for the age of the expendable components.

The service life is based upon manufacturer's recommendation, service conditions, maintenance history, operating experience and test and inspection results.

When the review of service life records reveals that a snubber is nearing the end of its design service life, efforts'are made to include that snubber in the next functional test cycle or the service life is reevaluated.

The purpose of the i.

l reevaluation is to extend the service life based upon experience and information gained during operations.

The results of functional testing and inspection may be used to alter the service lives of all snubbers of similar design operating under similar conditions.

l l

i i

Amendment No. 103 236b-l

\\

-

ML20090B459

Text

Attachment:

Navigation menu

Search