ML19275J341
| ML19275J341 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/20/1976 |
| From: | GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT |
| To: | CLEVELAND ELECTRIC ILLUMINATING CO. |
| Shared Package | |
| ML16341B552 | List:
|
| References | |
| CON-044549-000, CON-44549 D-809-044, D-809-44, NUDOCS 8104020115 | |
| Download: ML19275J341 (1) | |
Text
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.m May 28, 1981 Doc 1ht ho.50-34S Director, Nuclear Reactor Reguiation U. S. Nuclear P.egulatory Conmission Washington, D. C.
2D555 Attention:
Mr. S. A. Varga JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 1 TECHNICAL SPECIFICATION UPGRADE Gentlemen:
In accordance with discussions with Mr. Ed Reeves of your staff, enclosed as Attachment I is the Unit 1 Technical Specification upgr&de package.
This package reflects Alabama Power Company (APCo) commants on the NRC draft version of the upgrade package with proposed changes indicated by a bar on the side of the page.
The intent of this proposed package is ta upgrade the Unit 1 Technical Specifications to the Unit 2 version to address outstanding licensing issues and requirements as they relate to Unit 1.
Certain items from the Unit 2 Technical Specifications were not included in this package because these items have not been generic issues on operating reactors and do not form a part of the licensing bases for Farley Unit 1.
In addition, changes have been proposed to the Unit 2 version which will require further discussions with the NRC staff.
These changes have been brought about as a result of experience gained by using the Unit.2 specifications.
In an effort to clarify APCo concerns, a discussion af the significant differences between the Unit 1 Technical Specification upgrade packege and what is presently in the Unit 2 Technical Specifications is provided in Attachment II.
This ettachment contains 22 items which have been divided into two categories based upon action APCo wishes to take on each of them.
These categories are as follows:
I.
Major item affecting plant availability without enhancing plant safety - not generic requirement for operating reactors.
II.
Item which requires clarification between the NRC and APCo on the design, licensing, and operaticnal aspect of Unit 1.
APCo proposes to defer any action en Category I items at this time.
It is requested that the current provisions of the Unit 1 Technical Specifications remain in effect for the Category I items.
For the Category II items, APCo has proposed these changes in Attachment I and wishes to discuss these items as part of the Unit 1 Technical Specification upgrade effort.
8107090115 810619 CF ADOCK 05000348 CF
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r; ', 20 1 The Fnvironmental Protection Flan (Appendix B to 0.L.) which adcresses nr.r._ra dini ng.i cal a s. art s nf nl ant nnerati nn.z, r, submitted to the NRC in r
AFCo letters dated May 19, 1930 6nd M.;ust 7, I?BD.
APCo requests that the Unit 1 Technical Specification upgrade license amenic,ent be made effective in thc fcilt.:#r.g *:arr.er:
Section
_ Effective Date Appendix A to 0.L.
1.
Definitions Prinr to startup followino the third refueling outage.
2.
Safety Limits and LSSS Prior to startup following the tnird refueling outage.
3/4 LCOs and Surveillance 3/4.1 thru 3/4.10 Prior to startup following the third refuleing outage.
3/4.11 and.3/4.12 Janua ry 1,1982
~~
5.
Design Features Sixty days after issuance of license amendment.
6.
Administrative Controls Sixty days after issuance of license amendment.
Appendix B to 0.L.
Environmental Protection January 1, 1982 Plan The Plant Operations Review Conmittee has reviewed the above proposed changes and has determined that the changes do not involve an unreviewed safety question as shown in the safety evaluation in Attachment 1.
The Nuclear Operations Review Board (NORB) will review the final upgrade package prior to issuance of the license amendment by the NRC.
The results of the NORB review will be forwarded at that time.
The Class of this proposed amendment is designated in accordance with 10 CFR Part 170 as a Class III change in that is deemed not to involve a significant hazard consideration.
Since APCo has submitted twenty-eight thousand dollars in fees to cover the outstanding technical specification change reouests which are incorporated in this upgrade, no additional fees are enclosed.
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In accordance :ith 10 DR so.30(c)(1)(i) tnree (3) sioned originois and thirty-sovon (37) additionni enpies of this oroposed amendment are
" :::i c:.ed.
Should you have any c;ues t r'.ms, pleese advise.
You.s trul,
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mn F. L. Clayton, r.
FLCj r/BDM:rt Attachments cc:
Mr. R. A. Thomas SWORN TO AMD SUBSCRIBED BEFORE fir. G. F. Trowbridge l'E THIS.2924 DAY OF Mr. E. A. Reeves 717#e-1981-Mr. J. P. O' Reilly Mr. W. H. Bradford
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Safety Evol w ;ica fu LaiL I Te b-i c:' S raci t i c s ti cn " _.: d.. c
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Subsequent to issuance of the Unit 2 Technical Specifications, the
- RC requested Alabama Power Ccmpany update the Unit 1 Technical Specificctions to ce censistent with those in unit 2.
In accordence with this request, the Unit 1 Technical Specifications were reviewed and chances proposed.
References (1)
FNP Unit 1 Technical Specifications (2)
FNP Unit 2 Technical Specifications (3) Outstanding Unit 1 Technical Specification Changes Subject Date Submitted a.
Radiological Environmental 10/10/79 Technical Specifications 9/02/B0 b.
Containment Purging 6/20/79 c.
Degraded Grid Voltage 10/10/79 d.
Fire Protection 1/03/80
~~(.
e.
Auxiliary Feedwater Pump Auto Start 2/28/80 f.
Operability of Equipment 6/02/80 9/10/80 g.
Administrative Revisions and NUREG-0737 1/1/81 Requirements 12/15/80 h.
Appendix "J" of 10CFR50 Exemption Request 2/02/81 i.
DNBR Limit for loss of Flow Transient 3/04/81 Eases:
Incorporation of these changes into the Unit 1 Technical Specifications will result in clarification of requirements, reflect resolution of several licensing issues, and incorporate the above outstanding revisions previously submitted to the NRC.
Tne proposed technical specificaticns are consistent with the plant safety analysis and commitments made to the h?C.
'.::: rm:nt i t rentn:;te;
": -- L' vontausicn:
it'e proposed changes to the Unit 1 Technical Specifications do not i no l ve an unrevierced safety question as defined by 10CFP.50.59.
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ATTACHMENT II Page 1 of 5 TECHNICAL SPECIFICATIONS
[&#D'N PROBLEMS ASSOCIATED WITil UNIT 1 g0060 6V IF UPDATED IDENTICALLY TO UNIT 2 oA d-r/DL APC PAGE SPECIFICATION CATEGORY DESCRIPTION 1.
3/4 0-1 3.0.3 I
APC's preference is for action requirements to start. at nine of (Motherhood) initial discovery of failure rather than time of failure.
No NRC generic requirement to incorporate in operating pla1ts.
Liv cussed at onsite meeting.
2.
3/4 0-2 4.0.3 I
Allows APC to perform surveillance prior to declaring eq'aiarent in.
(Motherhood) operable, i.e., if surveillance test was not perf ormed on tine, then surveillance can be performed rather than declaring equipmant incperat it.
No NP.C generic requirement to incorporate in operating plants.
Dis-cussed at onsite meeting.
3.
3/4 3-4 Table 3.3-1 Item 20 II APC proposes to make 3.0.4 not applicable to ACTION STATEFENT 8 UaSb/OSI (Reactor Trip which is for the Reactor Trip System Interlocks.
No safety analysis l
. System Interlocks) invalidated by change.
Only by making 3.0.4 not applicable to reectm
(/d56ASJ/5/)*
trips would invalidate safety analyses.
4.
3/4 3-19 Table 3.3-3 Item 4 II APC prefers to make Steam Line Isolation not applicabic in modes 2
'3-20 (Steam Line and 3 if MSIVs are closed.
3-23 Isolation Actuation)
This is a conmon sense approach.
The current Specification woule roc uit e 3
a change to a lower mode to perform instrumentation n'aintenance in scme situations even if the MSIVs are shut.
Discussed at onsite acetin).
S.
3/4 3-19 Table 3.3-3 Item 4.d II APC prefers to add bypass below P-12 for Tavy Lou-Lle.
h S S /aS/ 7
!NSEioS"Sctuation)
Same argument as Item No. 4.
oiscussed at onsite meeting.
(/CS8 A.tr/sr)
Page 2 ( f 5 ATTACHMENT 2 (Continued)
APC PAGE SPECIFICATION CATEGORl DESCRIPTION G.
3/4 3-22 Table 3.3-3 Item 8 II APC prefers to add 3.0.4 not applicable to ACTION ST ATEf1EllTS 20 4:rd 7
(ESF Interlocks) 13 which are for the ESF System Interlocks.
Same argament
,IM U I.
as Item 3.
J. A dom 7.
3/4 3-36 Table 4.3-2 Item 6.a II APC wants to exclude automatic actuation logic for tr"p o' niir 3-37 (Aux. Feed. Actuation) feedwater pumps for auto start of AFW, Accident ein31y s i s dott. io t gSS/OJr :
take credit for this start signal.
FNP design does not allow testing via solid ; tate protectic>n
(/CSSM.ssur) system.
Cannot be tested at power.
8.
3/4 3-49 3.3.3.5 Instruments I
NRC oroposes i.o reduce tCO ACTION STATEMENT from 31 d6y:, to / ta't.
/S8/0TE HSD jgg No NRC generic requirement to incorporate into operitting plant 9.
3/4 3-57 Table 3.3-11 II APC prefers to utilize pressurizer SV discharge temperature
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( Accident Monitoring if limit switch fails to extend LC3 to 7 days since only one O
Ins trumenta tion) limit switch is available.
(/)CS//CSd Mdr)
L 91 cal aoproach to allow operation until weekend to repair sinc 2 backup indication exists and only one limit switch in:;t.illed.
10.
3/4 3-72 3. '). 4 I
No NRC generic requirement to incorpora te into opc i tin ; y ut.
3-73 (Turbine Overspeed (Unit 2 only)
Protection) 11.
3/4 4-8 3.4.5 11 APC prefers to perf orm surveillance test in C10, i f not per-(PORY Block Valves) formed in the previous 92 days, to preclude blowing 'ialve packing while plant operating.
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Pa ;c 3 of 5 ATTACHMENT 2 (Continued)_
APC PAGE SPECIFICATION CATEGORY DESCRIPTION 12, 3/4 6-8 3.6.1.6 II APC prefers the following for tendons:
(Containment Tendon 1.
Acceptance criteria to be above 40 year limit.ratier f.han p e ji:b 9
Surveillance) limit because 40 year limit is the design limit fcr the ter.h r:.
[68[O6 2.
Only detension one in each group (done, "(rticci, hoop).
J Detensioning tends to be counter-productive at d (:nhanc e: to probability of damaging individual wires withcut gaining ar.y significant informction from the process.
13.
3/4 7-13 3.7.5 II APC prefers seven days to three days for the ACT10ll STATEMElli (River Water System) because FNP his closed service water system.ind pcnd Joe ultimate hea c sink.
ggg
[ / W 8 / D 2 d.55 G 7) 14, 3/4 7-21 3.7.9 II APC prefers the following for snubbers:
7-22 (Snubbers) 7-23 1.
NRC 120 day letter response.
7-24 B3/4 7-5 2.
Acceptance criteria for mechanical snubbers to t11ou mt.nue testing.
(No test equipment is available.)
3.
APC prefers to limit engineering evaloa tion I.o th r;.-
snubbers that are locked up.
Also to 1i nit evi ua tion to component ra ther than system.
15.
3/4 7-85 3.7.11 II APC prefers to utilize a fire patrol vs. a continuous fire 7-88 (Fire Protection) watch.
7-94 B3/4 7-7 C68/06
ATTACHMENT 2 Page 4 of 5 (Continued)
APC PAGE SPECIFICATION CATEGOR_Y DESCRIPTION 16.
3/4 7-65 3.7.13 I
No NRC generic requirement to incorporate inta operatiail plant.
7-66
( Area Temperature (Unit 2 only) Monitoring) 17, 3/4 8-1 3.8.1.1 I
No NRC generic requirement to incorporate into opera ;ilg plant..
thru 3.8.1.2 3/4 8-8 (Diesel Generators)
B3/4 8-1 (Unit 2 only) 18.
3/4 8-9 3.8.2.1 I
No NRC generic requirement to incorporate into opera;i19 plant.
8-10 3.8.2.2 (Unit 2 only)
(Inverters) 19.
3/4 8-12 4.8.2.3.2 I
No NRC generic requirement to incorporcte into operating plant.
8-16 4.8.2.5.2 B3/4 8-1 (Batteries)
(Unit 2 only) 20.
3/4 8-18 3.8.3.1 I
No NRC generic requirement to incorporate into opera tioq plir:;.
thru (Containment Pene-3/4 8-28 tration Overcurrent (Unit 2 only)
Protection Devices) 21.
3/4 8-29 3.8.3.2 I
No NRC generic requirement to incorporate into operatinc plmt.
thru (MOV Thermal Over-3/4 8-32 load Protection (Unit 2 only)
Devices) i
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ATTACHMENT 2 Page !i of 5
_ Continued)__
(
APC PAGE SPECIFICATION CATEGORY DESCRIPTION 22, 3/C 11-15 3.11.2.5 II APC prefers to change 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to immediately.
It nur ;,i <e imre than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to reduce oxygen content.
NO Logical change that reduction of Og should st.irt invie ji.itely; however, may be impossible to meet specification within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
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3.0.1 Cemplience -ith the Li=iting Conditions fe. C;eration : r.tained in th:
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- nditi ns spacified therein; ax: apt that u; n f:ilure to ceet the Limiting Centiti:n f:r Cperatien, the ass:ciated ACTION requirerents shall be r.at, 3.0.2 Nen :: liance with a specification shall exist wnen the requirements of the Limitiac Caacition for Geeratien anc associatec ACTION require:ents are not met within the specified' tite intervals.
If the Limiting C:ndition for Operati n is :::: red rier to expiratien cf the specified ti=e intervals, cc: pie:1cn 0,, tne r,C_iv.N, requirements is no. required.
3.0.3 Wnen a Limiting Ccndition for Operation is not cet, except as provided in the associated ACTION recuirements, within ene hour ACTICN shall be initiated to place the uni: in a MODE in which the specificatien does not apply by placing it, as applicable, in:
1.
At least HOT STANCBY within the next 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, 2.
At least HOT SHUTDOWN within the fc11: wing 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, and 3.
At least COLD SHUTDCWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
g -
Where c:rrective easures are cc pleted that per=it cperatica under the ACTION requirements, the ACTICN may be taken in ac:Ordance with tne specified ti=e li=its as reasured free, the time of {ailure to meet the Limiting Conditien for g
Cperation.
Excepticas to these requr rements are stated in the individual specificaticns.
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- 3. 0. 4 Entry into an CPERATIDNAL MODE cr other s:ecified c nditi:n shall not be made unless the ::nditions of the Limiting C:ndition for Operation are ret with ut reliance :n previsions contaired in the ACTICN recuirements.
This provision shall not prevent passage through OPERATIDNAL MODE 5 as recuired to cc ply with ACTICN requirements.
Exceptiens to tnese requira:ents are stated in the individual specifications.
3.0.5 When a system, subsystar, train,
- enent or device is deter =ined to be inoperable solely because its emergency p wer scurte is ineperatie, or solely because its normal p:wer scurce is inoperable, it :ay be c:nsidered OPERAELE for the purpose of satisfying the recuirerents of its applicable Li=iting Condition for C:eration, previced:
(1) its corresponding normal or emergency pcwer source is CPERABLI; and (2) all of its reduncant systa (s),
subsyste (s), train (s), cc p:nent(s) and device (s) are OPERAELE, er likewise satisfy the recuire:ents of this s;ecification.
Unless both conditiens (1) and (2) are satisfied within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, ACTION shall be initiated to place the unit in a MODE in which the a;plicable Limiting COnditica for Cperation c:es not apply by placing it, as applicable, in:
A FARLEY-UNIT 4
3/4 0-1
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1.
At least HOT STA'CEY within the r. ext E burs,
_,. -..,..rviuv-n within t.,.e,,oe,0.,ng a neurs, anc c.
n: r eas t e,v i 3.
At iees: COLD SHUTDC4N within the sucsecuent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
inis srecification is not applicable in MODES 5 or 6.
- 4. 0.1 Surveillance Recuirements shall be applicable during the C?ERATICRAL MCDES cr other conditiens specified fer individual Limiting Cercitiens for Operation unless other<ise stated in an individual Surveillance Require:ent.
4.0.2 Each Surveillance Requirement shall be perforced within the specified time interval with:
a.
A :sximut alicwable extension not to exceed 2E% of the surveillance interval, and -
fi
&y h5 b.
The :::bined time interval for any 3 conse:Utive surveillance intervals not to exceed 2.25 times the specified surveillance interval.
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Md, 4.0.3 Performance of a Surveillance Requirement within the specified f? time interval shall constitute compliance with CPERABILITY recuirements
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for a Limiting Condition for' Operation and associated ACTION statements unless otherwise required by the specification.
Surveillance Require-(_
ments de not have to be performed on inoperable equipment.
4.0.4 Entry into an OPEP.ATIONAL MODE cr other specified conditien shall not he made unless the Surveillance Recuirement(s) assceiated with the Li:iting Ccndition for Operation have been performed within the stated surveillance interval er as Otherwise specified.
4.0.5 Surveillance Requirements for inservice inscettien and testing of ASME Ccde Class 1, 2 and 3 cc ponents shall be applicable as fellcws:
a.
Inservice inspecticn of ASME Ccde Class 1, 2 and 3 cc:penents and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be perferred in accordance with Secticn XI cf the ASME Eci'er and Pressure Vessel Code and applicable Acd=nda as recuired by 10 CFR 50, Section 50.55a(g), exce:t where scecific writtan relief has been crantec by the Cc :ission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
b.
Surveillance intervals specified in Section XI of the ASME Eciler and Pressure Vessei Code and apolicacie Addenda for the inservice inspection and testing activities recuired by the A5ME Eciler and Pressure Vessel Code and applicaole Acdenda shall be applicable as fc11cvs in these Technical Specifications:
FARLEY-UNIT 1:L 3/4 0-2
_ATT;::/I: LITY EU;H ILLANCE REOUIREMENTS 1.
At least HOT STAND 5Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.
At least HDT SHUIDC'n'N within thc fclicwing 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, and 3.
At least COLD SHUTD0'a'N within the subsequent 24 nours.
This specification is not applicable in MODE 5 5 or 6.
4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an inch C al Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall De performed within the specified time interval with:
a.
A maximum allowable extensicn not tc cxceed 25% of the surveillance interval, and b.
The combined time interval for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.
Exceptions to these requirements are stated in the individual specifications.
Surveillance Requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:
Inservice inspection of ASME Code Class 1, 2 and 3 components and a.
inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except wherc specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55e(g)(6)(i).
b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
FARLEY-UNIT 2 3/4 0-2
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t4 7
TAnl.E 3. 3-1 (Continucil)~
Ei M
REACTOR lillP SYST[ll lilSillllMEllTATIOil rep tillillfull p
TOTAL 710.
CilAlli1El S CllAfillEl S APPLICAlllE futiCTI0llAL UillT OF CilAllilELS TO THIP OPEllAlllE fl0DI3 ACTI0li 17.
jurbine Trip g
A.
Low Auto Stop 011 Pressure 3
2 2
1 7g II.
Turbine Throttle Valve 4
4 4
1 7
Closure 10.
Safety Injection input from ESF 2
1 2
1, 2 1
19.
IIcactor Coolant Pump Dreaker i
l'osillon Irlp A.
Above P-8 1/ breaker 1
1/ breaker 1
lu g 11.
Above P-7 1/ breaker 2
1/ breaker 1
11 t>3 per oper-s atinu loop Ed 20.
Ileactor Trip System Interlocks A.
Intermetliate Hange lleutron Flux, P-G 2
1 2
2, a nil
- O' g I
i 11.
Low Power Heactor as Trips lilock, P-7 P-10 loput 4 2
3 1
0.y P-13 loput 2 1
2 1
0 C.
Power itange llentron i
flux, P-0 4
2 3
1 0'g D.
l'ower Range lieutron 4p ilux, P-10 (Input to P-7) 4 2
3 1, 2 0
E.
Turisine Impult.o Chamlier ih Pressure, P-13 2
1, 2
1 0
F.
Power llange fleutron 4
2 3
1 0' y
}
s
(~ lux, P-9
g TAELE 2.2-1 f : :ti.ted) s A~.TICh 5 niLh the interic k inwer= :le to t'.e extent that a res;t:.r tri:
6 i
s.
s muca snound no..g.e w, w. sn.ua wr: uu r,..-.:.
as
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ceciare :ne trip fun::1:n in; erapie an: f el i c w
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statements o,., sable 1 for tne atie.tec nanne us).
s.--
Interic k Affectad Char.r.als en Tchie 2.2-1 I
Source Range, Neut n Flux Startup Shutd:an
- 2. F-7 a.
Lew Reacter C clant L: p Flev (2 l eps) 5.
Underveltage - React:r C clant P=:s c.
Uncerfrecuency - React:r C alant Pu._ps d.
Pressuri:er L:w Pressure e.
Pressurizer High Level
- 3. P a.
L w Reactor C oiant Loop Flew (1 loop) a.
surtine irlp
- 5. P-10 a.
Intermediate Range, Neutron Flux b.
P wer Range, Neutron Flux - L:w Setecint curce ange, Neutron riux-c.
e n
Startup V
Shutdown d.
P-7 (Ita: 2 above) u,-
- 6. P-23 a.
P-7 (Item 2 above)
ACTICN 9 - With a channel associated with an Operating loop inoperable, restore the ine:eracle enannel to CPEFAELE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> er be in HOT STANCEY vithin the next 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />; however, One channel assceiated with an Operating leap may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specificatica 4.3.1.1.
ACTICN 10 - With one channel inoperable, restere the ineperable thannel to CPEFAELE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THEPP.AL FCWER to below the P-S (Lew Rea--
Nalant Pu..; Flow and Reetter C:oiant P=p
. Breaker ?:sition) setpoint within tne next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
CTeration belew the P-S (L:w Reacter C clant Pur: Flew and P.eact:r C clant Pu= Breaker Position) set oint may continue pursuant to ACTICN 11.
r FARLEY-UNIT 2
~~
3/4 3-8
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~
/
- n.. a i.:.
.,.nT..m...ni__
t
\\
a" Trip functicn may bc typ2:re in nis MODE belcw the P-il.
(?ressurizer Pressure M oc( of Sauty injec.icn) serpcin:.
a" Trip functica ay bc typarted in this M00~ beicw P-12.
(T, Eicek of Safe y Injaction) setpcint.
su"The cnannel(s) associate witn the pectective functions deri.el fra tha cut of service React:r Coolant L::p shall be placed in the trippe: :::e.
"The previsiens of Specifica:icn 3.C.4 are not applicable.
N jjf-0.pkI(fIhifdl*d2&m$i b Vd440GC d##
a ACTION STATEMENTS ACTICN 13 - With the number of CPEFAELE channels one less than the Toul Nu= er of Channels, be in HOT STANO3Y within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and in CDLD SHUTDOWN within the folicwing 30 hcurs; however, one cnannel may be bysa: sed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance
'.esting per. 5pecification 4.3.2.1 provided the :her cha..:i.
- w: -
i s w,-..- L t.
ACTION 14 - With the number of CPEFAELE channels cne less than the Total
(..
Number of Channels, c:eratica cay proceed until perf r ance of the next recuired CHANNEL FUNCTICNAL TEST proviced the I'
incperable channel is placed in the tripped :ndition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTICN 15 - With a channel associated with an c;erating icap ineperable, restere the incperable channel to CPEF.AELE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STAND 5Y within the next 5 heers and in at least HOT SHUTC~dN within the felicwing 5 h urs; h: wever, cne channel associated with an operating icon cay be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.
ACTICN 15 - With the nu-ter of CPE?.AELE channels one less than the Tetal Nu :er of Channels, cperation may proceed pr:vided the in::erable channel is placed in the bypassed tendition and the Minicu Channels CPE?aELE recuirement is demonstrated with2 n 1 heur; cne acditional channel say be bypassed for to to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for su-veillance testing par Specification 4.3.2.1.
- m. u CN 1/ - With.sess than tn.e Minimum v..anness Cr-.w. L:, Operation Ey
-u t
continue provided the ::ntain ent purge and exheest valves are raintained closed.
ACTICN 15 - With the number cf CFE?.AELE Channels one less than the Total Nu=er of Channels, restere the in::erable enannel to C?E.AELE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> er be in et least FOT STANDEY within the next 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and in CDLD IMUTCdN within the folicwing 20 h:urs.
FARLEY-UNIT Q 3/4 2-23
i
(
TAlllE
.3. 3-3 (Continuedl EllGillEEllED SAFETY TEA 1UitE ACillATI0ld SYSTEll lilSTillliiffliA110!!
Q b
111111111111 T
10IAL 110.
CilAllilEL5 CllAllllEI.S APPLICAllt E i
p ft!!1CTI0llAL UlllT OF CllAfillELS TO lit 1P OPEllAUL E 110 DES _.
.A_I; T I_O'.l 7.
LOSS OF POWER a.
4 kv ilus 3/ilus 2/Dus 2/Ilus 1, 2, 1, 4 19^
loss of Voltagu b.
Grlil De[1 railed Voltage 3/Dus 2/ilus 2/ilus 1, 2,.1, 4 l'l*
0.
IllGillEEitfD SAFETY TEAlliitE ACIUAlloll SYSilH liiTEl(LOCKS s
N a.
Pres.arlier Pressure, 3
2 2
1, 2, 3 241 P-il 0
h.
Iow-low Igyg, P-12 3
2 2
1,2,3 2ilip c.
Steara Generatur (Sec 5.a above) level, P-14 d.
Itcactor Trip, P-4 2
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(1) Manuai actuation s-r cnes snaii ce T.asted at least once ser
.o
..c o...a.
curing snutec n.
- t. l i c ner circuit:j asscciatec witn manuai stiegueres acuatien snall receive a CHANNEL FUNCEONAL TEST at least once per 31 czys.
(2) Eacn train er iccic channel shall be tested at least avari Z days n a 1 e e,ue.:n:- - _ - D e n.,. z...u.
- n (3) Channel calibration shall exclude actuatica cf tne final trip ac*uation relay.*
(4) Functional testing shall censist cf verification of relay c:eration ucen rencval of input vol:. age and cperation of 2-cut-cf-3. Icgic tx:luding the final trip actuatien relay."
(5) If not perforced in the previcus 92 days.
(& &ck&paa%2ke M Ie' or Mp pwk&n%2r pwmps.
f "Actuamen c-.ne final trip a:: cation relay shall be included in res:ense time testing.
FARLEY-UNIT 1 1.
3/4 3-37
. ~..~... ; c.. r. _..,
,r r
-_.__ wu i uuna 2:e i nu.mru ru r "i e.r.; i :
t'"TT"C CONDITICN 00? OPEFAT K.N w
- 2. a..e...:.
4 a. - _.., :..... a.v,.
i n s..._ e n.-. c n c.a.-.. s.c....n i n c.
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s ACTICN:
With the nuccer of C?EFABLE re cte shutdown scnitoring cnannels less a.
. o_ _c.,..
6.e :...- e.
_x. i....a.. 1
+.c
. 6.cn. e.-..:.s.
w,y s c_w, ;.
c OPEF.ASLE status within/ cays or te in HOT SHUT"nN within the next l
12 hcurs.
3l The provisions of Specificati:n 3.0.4 are not applicable.
b.
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- 4..=. 3. 5
~
demonstrated CPE?.AELE by performance cf the C:'ANNEL. CHECK and CHANNEL Cn.L-:?n,_,Ach, :perattens at tne frecuencias snewn in s acle,,...
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. n, -, n. u.
n.o c y --, n..,
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3.4.5 All Ocwer relief valves (.L0nvs > an::.neir asse:iatec bic:k vaives snall se CPEPABLE.
nr u um= 2,..TT,:
h.....,ours., 2, and 2.
,. -..N:
c i n.
a.
Witn one or m:re PCEV(s) incanMe, witnin i hcur either restere the PCEV(s) to CPE;ASLE status er ciese the asse:iated bicck valve (s) and remove pcwer frem tne ciccx valve (s); cinersise, be in at least HOT STANCEY within the next 6 er s and in COLD SHUTDCWN within the follcwing 20. hours.
b.
With cne er more block valve (s) '.::eracle, within i hour either restore the block valve (s) t: C:::JELE status or lese tne bleek valvt(s) anc remove p:wer fr : the bicek valve (s); othersise, be in at least HOT STANCEY within the ne.xt 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and in CCLD
.c,nb.,,..N w1. hi n...e,. ol.icwing av, neurs.
u auun c.
The previsions of Specification 3.0.4 are not applicable.
\\
.cL,~V:_ T. s u.N -:
- m.,JI ~.:_u.:N~: _c n
r _
n 4.4.5.2 Each PCEV shall be demonstrated CFE?.ASLE at-least ence ;er 15 : nths by erfor: ance of a CHANNEL CALIERATICN and cperating the valve througn ene cycle of full. ravel.
M,ns e==k CcLb 5%Tbxml IT nm fer2~rmeA..d e f *' ".
- 4. 4. 5. 2 Each block valve shall be ::emonstrated CPETABLEge '--.
. cw_3,
92 cays by Operating the valve thr ugn One :Orplete cytie of ful' travely arc O'.2 dboCA. VO!A^L 1.S C{C&td W01 UL WWMmWdm wErb YfMtWrEi YW WY h Yh h)Y. G Or b, C S VC..
lW OCTIO/J FARLEY-UNIT h 3/4 4-3
... ~_,..
u. o n....._ u. o w m.o-
-...--..m._.
a.. a n.... :..
,a..w...
T ] u. T. ** T. N. G m_,. 'nT. '.ri n e. u T. O..D. o..p. p t.} } @'
~.
~ ~.
. c.... A.,
- n...._......_,_ :..
e _ty or the.containent shall be naintained at a level cenrin-nt with the requirtn.ents in Specific:.ti:n 4.6.1.6.
.t.o u..r.. c.e sT._r._T v_ v..
.u.n. _nr _e$.,
9, 2 34 4
/3CTION:
If an engineering evaluaticn perferned in accordance with the surveillance require ents for this secticn dete =ines that centai =ent structural integrity is adversely affected, restete the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least liOT STANDET within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and i._ CCID Sh'h'TDC E within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
.et Rvr.T.T.T._: yur p..n.t 1. rv v-s e
r
.m u
4.6.1.6.1 Conta4-ent Tendons The centainment tendens' structural integrity shall be den strated at the end of one, three and five years following the initial centai=ent structural integrity test and at five year intervals thereafter. The tencons' structural inte rity shall be denenstrated by:
s Deternining that a representative sample of at least 21 tendons a.
(6 done, 5 vertical and 10 hoop) each have a lift off force within the predicted limits, defined as not less than the predicted loder li=it nor greater than the allowable uppe 14 force per vire at the tine of the test as shown in Figure 4.6-1.
The number of broken or danaged wires shall be dete::ined by a visual inspection of the tenden end and by the lift off test.
If the lift-off force of a selected tendon in a group lies between the predicted lower limit and the 40-year lower linit, two tendons, one on each side of this tendon shall also be checked for lift-off force.
If the lift-off forces of these two tendens are within the predicted limits, the single deficiency nay be consicered as unique and acceptable.
If the lift-off force of either of the adjacent tendens as re[erenced above, or core than ene tendon in tb: original sanple set lies between the predicted lower limit aad the 40-year lev-- '#-4*
an engineering evaluation sh:11 be performed to deter =ine the need for any corrective ceasures and/or additional su:.eillance requirements.
-~
e Gew7 aw.t 34 C-8
n, u.,r
.c y c.r. e m...e e
or 3/t. 7. 5 RIVER WATER SYSTEv t in i n t:n ~~t;ni iip u c..0 ccie:.i~ m:
3.7.5 At least t-c independent rher -ater iceps shall be CFE?aSLE
- :. at least two river water pt=ps per lecp.
- n. o. i.t r a.r i m.
uv. e..c,., 2,
,e
.a -
-.a a n a,.
s
- r. u"T. F...
7 ys
- 'ith Only one ver water leep C?E?MLE, res cre at least two iceps to "Pr"*"'
n status within _? " 7 er be in at least HOT STAND 3Y within the next 5 neurs and in cLD SHUTDC'.a witnin the felicwing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREuENTS 4.7.5 Each river water ico; shall be demonstrated CPE?.ABLE:
f-a.
At least once per 31 days by verifying that each valve (manual,
.2 - -
power operated or automatic), in the flew path, servicing safety I
related equipment that is not iccked, sealed, or othe: vise secured in positien, is'in its correct position.
b.
At least ence per IS months during shutdown, by:
1.
Verifying that each autecatic valve servicing safety related equip. ment actuates to its corn ct position en a icw pond level signal.
2.
Verifying that the buried piping is leak tight by a visual inspection of the ground area.
we o
FARLEY-UNIT X 1-3/4 7-13
C a.;
d' ~
W"lt i i! !!L E ".~ OU1 hEFEiwT 5 E D m s o snme s b.
Visual InsDecGun 'cce tEnce Critcria Visual inspecuens sndii verify (1) Lect there sia T.
.i;i:10 #.di: -
tions of demera nr innairea OPERASILITY, (2) attachaents to tha foundation or supporting structure are secure, and (3) in th:sc locations where 3.,us,er twecent can be manually indu::d vitbe"t disconnecting the snubber, that the snutter nas freece ci ouverent and is not frozen up.
Snubbers which appear incperable a a result of visual inspections may be determined CPERABLE for the purpose of,
establishing the r. ext visual inspection interval, providing that (1) the cause of the rejection is clearly established and reredied for that particular sr.utber and for other snubbers that may be generically susceptibie; and (2) the affected snubber is functionally tested in the as found condition and determined OPERASLE per Specifications 4.7.9.d or 4.7.9.e, as applicable.
However, when -
the fluid port cf t hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection internal.
All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
F c.
Functional Tests
(
l
' = "
e s'-
Q t once per 18 months durin n, a repres of 10.
v.
" + otal of each type of snUm in the J~..
oe a plac
= " ;n te.
C sho be functiorad Q ad ei'" - not meet the
.._ q l
- d %
7*-4 + For eac..
oe of snubbe-Specification Ce...
a 7.9.e.
.. _ d 'ional eptance ci s
"bber shall be fun".onally ter m -.. "
q e that * ~e hw'th ' all snub'. s have been, unctionally 10P g found or failun-aed.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range o_f size and capacity of snubbers.
At least 25% of the snubbers IE..
In tnePrepresentative sample shall include snubbers from the follcwing j
three categories:
1.
The first snubber away from each reactor vessel nozzle 2.
Snubbers within five feet of heavy equipment (valve, pump, turbine, motor, etc.)
3.
Snubbers within ten feet of the discharge frc a safety relief valve t
i FARLEY-UNIT /
3/4 7-21
Insert to
- .'.9.:
_..,.___.,_+n., e.-__;;
I
. u..... a ~.,
___c__
e
,.,.,.__._______s..n
..m.,.
.....r..
of 85 srubbers shull La furcticnall3(:csted cither in pl :: cr in a bench I
test.
.f mare than 3 snubber; do not ce: the functionai tes; acceptance 4.7.9,.d o,r 4.7.9.e, an additional sempla s=lected criteris Of Sp :ifi:: tic.
e
.ce tunctiona6,sy,&cs.em, onara &
accorcing to In2 expression ceta-of sna r i u
is the total n.. bar of sn bbers found incperable during the functi:nal o
testing of the initial representative sample.
Functional testing shall continue according to the expression (22)b where b is the number of snubbers found inoperable in the previous re-sample, until no additional incoerable snubbers are found within a sample or.until all snubbers in Tables 3.7-4a and 3.7-4b have been functionally tested.
Snubbers greater than 50,000 lb. capacity may be excluded from functional testing requiremants.
PLiVT'5YSTEMS
/*
/
Sun v 1;,Ls.L:.g._
.-._. (Lencintec) 3
%:vul : 07:
i Snebbers icentified..in Tacles 3.} de and 3.7-L5 es Espacially v1...
m a
-,,1cu i o neccve" or in,... h nac.. tion tcnes --c.o; m..tc;-n n>g ia shall also ha included i.n the represantativa. sampla.".icc:as 3.7-4a and s... / -o cay ce usec aciat,.y or separa eiy as th= csis ;cr t.,.a stapling plan.
In addition to the regular sa:ple, snubbers which friisd the previcus functional test shall be retested during tne naxt tas: ptried.
If a spare snubber has been installed in place of a fatiad : utber, then both the failed snubber (if it is repaired and installed in ancther position) and the spare snubber shall be retestec.
Test.esults of these snubbersh+may not be included fc-the.re-sar linc.sim.cedilae.
SQ 4.
shute res:tHn cddiflcnot.hedl cut rb43 dven If any snubber selected fer functional testing either f ails cc loc.'<cp or f ails to uove, i.e., frecen in place, the cause vill be,
evaluated and if caused by manufacturer er design deficiency all snubbers of the same design subject to the same cefect shall be functicnall.v tested.
This testina. rec.uire:ent shall be indecendent cf the require:ents stated above for snubbers not cee:in; the
~
functienal test acceptance criteria.
r to be fec'r<.e4 up
%e sndbers are. aMed T'-
For the snubber (s) fcundg ::c--b:c, - engineering evaluatien shall be perferred on the cc pcnentsphich :: :ri;WW ": :Uh-':b The purpcse of this engineering evaluatica shall be to determine if
- - _u. ? ~
- +u.x.
+u
..>u~
.u.
une,_z...,.+ w.u;-:..,...
a.
- -~
n...
n s u, ~
.u.
...u y.,-u,--
a
_._,./....
c 7;:.rs cc:penent ra:ains capable of teeting the designed service.
d.
Hydraulic Snubbers Functional Test Accectance Criteria The hycraulic snubber functicnal test shall verify that:
Ar 1vation.(restraining act1ca) is acnteved wl nin ne spec 1,. led rance of velocity cr acceleratien in both tension anc cocpression.
2.
Snubber bleed, cr release rate, where required, is within the specified range in ec=pression or ensicn.
ror snuccers specifically required to not displace under continuous lead, the ability of the snubber to withstand load without cisplacement shall be verified.
= Fer:anent or other exe:ctions frc: functional testing fer individus1 snubcers in these categories may be grantec by the Cctrissicn caly if a justifiacle basis for exe:ptien is presented and/cr snubber life cestructive tescing was perferred to cualify snubber cperability fcr all design conditiens at either the cc pletion of their fabrication or at a subsequent date.
FARLEY-UNIT b4 3/4 7-22
ut1.M i.5 n h..s f
!~
SU:vEn.U.Nc: P:n!!I: ur Ts (centi.eed) s e.
Parnanirsi Snu:cers Functional Test A :ectance Criteria The.= !,c.ical sr.ubber functicnal tast shali.cifj t'ct:
(T..e force W.itiagfrca acgr.t pf '" sr.Lbbg rcd is ses_ m n :n. :ecli -
traxicum cT v
. ens m.. cc ; d:rac5all.^* h='
' \\easec d tha.
dru ft Drag is
/b d.-
' a. s *..
/
.,..y..e....".....=..
< -m.....
e _.. n. e~
a
. m..c al nl...
.. n).
_ ~ a a, _..:. u
__ r
.2
,.. o.
g e cf
- e. -dty or
.eie..-#c o c.~ tens and c. are..cn.
SnuCL
_Qa e - rate,
- e recuired, ithin 4e N.-ified
.xnce in cy. csic~ r n.cion.
Fc snucc.
s..cas, f
ang M -a y.0; t
.- lace unce. --
.nucus ice" QJ7_%'
.o withs.and ice:
.t...."t cis' _mecentf_ge ver%1ef 1, h e.
snv'cbar ei rek d6P 90 o&- + cave}
in bo+h tension and ccaf res= ion 4.The sno b ber der: twt exhibit irre.3olv
+m ve l cn~ 0%C t Indic8 ions o5 inYcena\\
geckonical interfereace.
FARLEY-UNIT T 4 3/4 7-23
r_....
5@ VEIL _mCE ~ EQU.;.E::075 (C:nti nued)
T.
- 0.. ' i = ; ::r.it: Lif ": i M - d ***'
record oi' Ge service lifc of,cach snubber, t he date tt ' hich the x
desicnated service life 00.
ences and the iles;ailatica end Cain-tr.nr...cc r:::rd: :n which the designated service life is based shall I
0 44 e/-
bc :::nta:nec as required by 5pecificati n 5.10.2.a.
[;.:2 tcphcc.d. a r f
7
--= =,,- - u E99h,, l. i L. W atis _da,t[ east 7[ ly cnte per 13 months N-
, the installation and maintenance f
re:Ords for each snutter listed in Tables 3.7-4a and 3.7-4b shall be reviewed to verify that the indicated service life has not been cxceeded or will not be exceeded prior to the next scheduled snubber service life review.
If the indicated service life will be exceeded prior to the next scheduled snubber service life revie, the snubber service life shall be reevaluated or the snubber shall be replaced or. re:Onditioned so as to extend its service life beyond the date of the next scheduled service life review.
This reevaluation, replacement or reconditioning shall be indicated in the records.
e
/~ -
W 3/4 7-24 FARLEY-UNIT $.
.q".._
[
F w %I4,
J4) d L f5J
- ?
s<.
?A5E5 3/t. 7.9 5tiu.u Eks All snd.ers are rc:;;ircd CT'EF.AELE te an:urc thct the It uctural integrity c; int cac cr ccclcn: sys:ce anc ali ecner seiny reiaced systems is maintained during and fciledng a sai::ic cr cth.r tvcnt initiating dynamic leads.
Snuccers excluded fr = this inspection pr y are these installed ca ncnsafety related systems and then only if their fcilu c cr failure of the syste: en vnich they are installed, wculd have nc =~v m e effect en any safety related syste.
The visual inspection frequency is based upon maintaining a enstant level of snubber protecticn :: systars.
Therefore, in: r:puir d i spection interval varies inversely with the etserved snubber f ailums anzi is cetemined by the nu:::er of incperable snubters found during an ins;ecticn.
Inspecticas perfer ed before that interval has elapsed may be useo as a new reference point to cetemine the next inspectien.
However, the results of sucn early inspections pe-formed before the eriginal requirec ; ire incarval has elapsed (nc=inal time less 250 may not be used to lengthen the recuired inspection interval.
Any inspection whese results recuire a shcr:er inspection interval will everride the previous schedule.
f When the cause of the rejection of a snubber is clearly estaclished and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functienal testing, that snubber may be exe:cted frem being counted as incperacle.
Generically susceptible snubbers are tacse wnich are of a specific make or =cdel and have tne same design features directly related to rejection of the snubber by visual inspection, or are similarly located er ex::csed to the same envirennental cenditions such as te perature, radiation, and vibration.
f
-h> be lockea UP Wnen a snubber is fcundf m~a:.e, an engineering evaluatien is performed O
dd4.f:-
- tt f:t r ' :t':- :' t : :~ :::- nt:
T-g--e 2_
r__
- 7 e
- ..._ _;.: g
- 7x _
.ct r_m_:f--7 u
e e - -._g 1.
.y..y-:
'2.c-cd b.
The engineering evaluation shall ceter=ine whether er not the snubber code of failure has imparted a significant effect or degradation en the so nem e s cc peneng e -e-Ws m.
off ac.he:d Tc provide assurance of snubber functional reliability, a representative sa. cle of the installed snucbers yill be functionally tested during plant f snutcc*ns at 16 =cntn intervass. p bserved failures of these sarple snubbers sna11 require functicnal testing of additicnal units.
Hydraulic snubters and mechanical snetters may each be treated as a dif'erent entity for the aseve surveillance programs.
Selec+lon o5 a represewhYWe sample acccedino 4de.
s etpess:on S5(l+ Q ) pec( des a canRdence level of ayn&&eIJ r
qs% %+ go% 4 go% & the Mubber.5 in & plairl~
wiIl be mWEAGL5 win:n accep%ce-hal&z FARL.r.Y-UNITI4 3 3/4 7-5
_ - - -' L* N ! _5 Y S 7 8. 5 I,
te:R. f ~s q m
- y vy c_ v,,
ev..e.. _u.._c s
"-~1v s
1_
um una v.,nu i m.
run m um. m..
- 2. 7. ". 2 The Sy=y and/or corinkler syste s listec in Taoie 3.7-5 shall be OPERABLE.
APP!.ICMILIT(: Wnenever equipment in the sprey/ sprinkler-protected crer.s is requirec to ce OPERABLE.
ACTION:
pg With one or =cre of the above required spray and/cr sprinkler systems a.
inoperable, within one bour estaclih.. e cendowns fire.watchEitha d m m.
5--kup fire suppression equipment y :.n:
systems er components c:uld be damaged; for other areas, estabiish a l
harly fire watch patrol.
Restore th? system to CPERABLE status wi:nin it. days or, in lieu of any oth[r recort recuired by Specifi-d cition S.9.1, prepare and submit a 5 ecial Report to the Ccamission pursuant to Specification 6.9.2 with.n the next 20 days outlining the action taken, the cause of the 'ne:erability and the plans and scnecule for rest: ring the systea ' CPERA5LE status.
b.
The pr: visions of Specificatien 3.
3 and 3.0.4 are not ar.plicable.
v-df~ /ea s 5 o rc a p r~ hout' SURVEILLANCE REOUIREv.ENTS 4.7.11.2 Each of the above recuired spray and/cr sprinkler systems shall be demonstrated CPERABLE:
At least once per 31 days by verifying that each valve (manual, a.
power operated or aut::atic) in the flew path in in its correct position.
b.
At least once per 12 months by cycling each testacle ' calve in the flew path through at least one complete cycle of full travel.
4 J
FARLEY-UNITl4 3/4 7-S5 15 5
,. r....aswa n.
ev a,
CD. SY5T;VE i ; s.TTu. m. e. nsnt T.i r..w :n. o n. o:s.tr..in. y 3.7.11.3 The folieving hign pressure and Irv pressure C0 rystems shall be 3
n;;s s oi :
E.
$ar~.'ica Natar Intaka $tTuctuTa (aaCh '133 Volt bus and 6ach COO ialt lead center - H?.
b.
Turbine Building 13 ten unit and distribution systa: in the Auxiliary Building - L.P.
c.
Diesel Euilding 5 ten unit and distributien system.
'P LIC'BILTTY: Whenever equipment prctected by the CO systems in required to 2
ce Ort.1n Lt.
4, 8
Pa t rol ACTICN:
a.
With one or nere of the above required CD systers inoperable, within one hour establi 5.a c' ^"=c:wo fi$e watch Kith backup fire ah o.wce-
~
suppression equipmentgwer cncse areas in which redundant systems cr cc:ponents could be carage for other areas, establish an hcurly fire watch patrol.
Restcr the system to CPERABLE status within 14 days or, lieu of any ct er report recuired by Specification 5.9.1, prepare and submit a Speci i Report to the Cctaissicn pursuant to s
Specification 6.9.2 withi ' the next 30 days cutlining the. action taken, the cause of the.i ccerability and the plans and schedule for.
restoring the system to PERARLE status.
b.
The provisicas of Speci icaticas 3.0.3 and 3.0.4 are not applicable.
af lead" csce per bour
.-m - v.:_NTS
_enRL:.L, ANL
~
n_n
~
4.7.11.3.1 Each of the above recuired CD, systers shall be de:cnstrated OPERABLE at least once per 31 days by verifying that each canual valve in the flow path is in its correct position.
4.7.11.3.2 Each of the abcve required icw pressure CD, systers shall be deracnstrated CPE?.ASLE:
a.
At least once per 7 days by verifying the CD, stcrage tank level to be greater than SC% and pressure te be greater than 250 psig, and b.
At least cnce per 18 months by verifying:
1.
The systa: valves and asscciated ventilatien da cers and fire ccer release mechanises actuate manually and automatically, cpen receipt of a simulated actuaticn signal, and 2.
Ficw frca each nor:le during a " Puff Test."
FARLEY-UNITkA 3/4 7-3
--;; :a* 5?5~~':5-
{_..
1/a.1 1 ? RIDE 9te:I:D crwE ; m nNS
._.-.=....u..
c c..n.-.. n_.u, e n. >. n..a r..:. m... e u,
.. ~
e*
-.-s._--nx e
3.7.12 All fire bar-ier penetrations (including ceDie penetration barriers, T h euvurs e,d fire dac.pers) iri fire L..e ;
da. ia; pr,tactir.; scfcty rtictcd
~e..
art:5 shall be functicnal.
APDLICAEILITY:
At all tines.
pired ar.d b ee #
f /ecsth:e se Aw ACT m :
a.
With on or more of the abcVe repuired fire barrie penetratiens non-f ctional, within cne hcur H t'-r, establish c.
- e fire watchbr at least one side of the affected penetratic.., cr verify tne OPERABILITY of fire c'etecccrs ca et least ene sice of the ncn-functional fire barrier, ww.- ; %.2d+x'. "n a::,i 4 Restore the r.cn-functional fire barrier pene.ratien(s) to functicnal status within 7 days or, in lieu cf ccy other report recuired by Specification 6.9.1, pre:,are and socmit a Special Report to the Ccmmission pursuant to 5;:ecificatica 5.9.2 within the next 30 days cutlir.ing the action taken, tne cause of the non-functional penetration and plans and schedule for restoring the fire barrier penetration (s) to functicnal status.
x i
b.
The previsions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REDUIREMENTS 4.7.12 Each of the above required fire barrier penetratiens shall be verified to be functional:
a.
At least once per 18 months by a visual inspection.
b.
Prior to returning a penetration fire barrier to functional status following repairs or maintenance by perfor;.ance of a visual inspection of the affected peretratien fire barrier (s).
d O
t crf FARLEY-UNIT k 3/4 7-F' c<.
l i
... -, = "..
et-~,
arz s
e 1
..s...,s
_..ne survelilance require ence previce asse ence tn.et tne cinimum ur u.ns:tITY requi rements o,. toe
..ie suscressicn systea.s are met.
u In the event the fire su;cressica water systa beccces inoperable, 4....-e.a,.,1....,..,.,
... e,.. c s..
v n...,4....,.. '. s e"1 c. a-
-. vi d.a s
- .5a.
w
.u
....w
. ~.
~.
n cajor fire suppressien capability of the plant.
ine requirement for a
.*e
._e..,.e.
, -..., e. s. o.,
- e..-. -.. -.. a.v a l "- = *.#.
.7 w 'e r.
........<-..u-...
.....f o...
r.
e the acceptability of the corrective teasures to provide adecuate fire n".-le-=
P an*..
l
- o..c.e j.., - - = k i '. i ',v
's o r ' '> e s....#... " c-d r
- .c-
- .#..r rn c# *'a.
a
.u s
.y.
--y-
..e
,9 T. O~ Da--10M
- - - 7.101 Fm' ~i 1 L da -
--- ~~
Ft b
3/~./. lu P
.mKM n
The functional integrity of tne fire barrier penetrations ensures that
'# es will be confined er acepuately retarced frc: spreading to adjacent, pertiens of the f acility.
This design feature minimizes the possibility cf a single fire rapidly involving several areas of the facility prior to cetection and axtinguishment.
The fire barrier penetrations are a passive element in 4.cee..i
.s.
. e. a..=.. i - n e. c -. *.*...:. ~d
.=. a.
e a".4e *.
+.a- -a.icdi-
- ". =. '. a 4.1 i '., '. #.. a en e.
r.
r Fire barrier penetrations are considered functional when the visually i
cbserved ~conditica is the same as the as-designed conditien.
For those fire barrier penetrations that are not in the as-designed condition, an evaluation
.. -jeir.=.i 7...
u' = s n *. d e e. =.d ed *.." e fi ra.
.eu.11.se e < -... u... sw..w.6.a.
.w.
.s w
e...
rating of the fire barrier penetra* ion.
WI During perieds of.ime when a barrier is not functional, either,1) an hour (y
:: fire wat n.s requirec to be raintained in the vicinity of the 7.:=,.., w; w....-.s.n
.2.
3c. sw... a.
s i - a. o f *.'. a.
a '. '. a... e d
.. -. lw.,. -. 2). u..
< e...
3
.c.
c.
e-r.-.
...x, w.
- e g-:.:.n. L:
v =.., 5 e e, -..s. u. a.
v e,.1, :, e A n>
c..
-o a
until the barrier is restcred to functienal status.
s I. /" '"
^
^*^
~l
...I.
The\\
\\
lN l\\
\\
t sure t,
.efet M te cruitra r,*
A,re:1. t :: rttura. iz. it i v as
%s b
ss jehe( t:
- c. yhen: e g rcrser. as g.
t
.vg gl,,f y r.c ati,r tamparate esg{grpps i n qxces empe turas, ycamper ::.e.Jh_f[its ece
- xpesu.
,c egcr, ive va. y et'icae'. ar
_an Ieck a 1. -
it. [ FE?ARiLjTY.
?ta
%dce 'an i icwanMer insk. rome.nt e. L r fTF.
FAF1EY-UNIT k i 3 3/4 7-7
o._
. -1.; c :.-- w - m 3
.ev e i r e v.re c. e. ur vm..e..r
.,.......--.,-......--,--.~.ns-,.
.,,.. ~..
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r - r. vr1 3.11.7.5 Tha concentration of crycan in any portion of the GASECUS RADwai:
TREAirENT SYSTB snall be limited to less tnan or ecual to 2% by voltre nenever the hydrogen concentration in that portion of the GASEOUS RADWA5TE TREATP.:Ni SYST8 exceecs 4% by volume.
a r e,.: tr e : L._.y:
nt all times.
i.
A CTION.:
a.
With the concentration of oxygen in the GASECUS PADWA5TE TREATMENT SYSTB greater than 2% by volume but less than or ecual to 2% by volume, reduce the concentration of oxygen to within tne limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b.
With the concent ation of oxygen in the GASEOUS RADWASTE TREAT"ENT SYST8 greater taan 4% by volume, immediately suspend all acditions of waste gases to tite system and gduce the concentration of cxygen to less than or ecual to 4% M
- e and less than or equal to Z%
by volume within the following 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />.
Immellotelf
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The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENT5 4.11.2.5 The concentration of hvdrocen or oxycen in the GASEOUS RADWASTE
~
TREATMENT SYSTEM shall be cetermined to be witilin the above limits by acnitoring the waste gases in the GASEOUS PADWA5TE TREATMENT SYST B with the hycrogen and/or oxygen monitors required OPERABLE by Table 3.2-14 of Specification 3.3.3.11.
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FARLEY-UNITk1 3/4 11-15