RNP-RA/13-0067, License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System

License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System

ML13262A008
Person / Time
Site:	Robinson
Issue date:	09/10/2013
From:	Wheeler S Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/13-0067
Download: ML13262A008 (16)

Text

H. S Robhnon $Wm 6~00* Plant WM12 391r ROWUr ENERGY 0:843W 851504 F: 84881 M*f9 Serial: RNP-RA/13-0067 10 CFR 50.90 SEP 1 0 2013 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 205550001 H. B. ROBINSON STEAM ELECTRIC PLANT. UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. OPR-23 LICENSE AMENDMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION (TS) 3.4.12, LOIN T*MPEIRTURE OVERPRESSURE P TECTION (LTIP) SYTMM

Dear Sir or Madam:

Pursuant to 10 CFR 50.90, Duke Energy Progress, Inc., formerly known as Carolina Power and Light Company, hereby requests an amendment to the H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP) renewed facility operating license DPR-23, Appendix A, Technical Specifications.

The proposed amendment would modify TS Surveillance Requirement (SR) 3.4.12.6, of TS 3.4.12, Low Temperature Overpressure Protection (LTOP) System, with a Note that does not require that the surveillance be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after decreasing the reactor coolant system (RCS) cold leg temperature to less than or equal to (s) 3500F which is the temperature when LTOP operability controlled by TS 3.4.12 Is credited. In addition, the FREQUENCY requirement is modified to simply 31 days. The note and FREQUENCY requirement are in accordance with NUREG-1431. Revision 3 and support the fact that the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> delay In performing the test provides the operators flexibift In priorities during the MODE 4 transition activities. In addition, the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> acceptability is based on the limited probability of a low temperature overpressure event occurring during this time period. Once tested, the SR Is performed every 31 days to ensure continued operability, which is the same requirement that Is in the current approved HBRSEP Unit No. 2 TSs.

The Enclosure provides the basis for the proposed change, including a detailed description, technical and regulatory evaluations, envirornental considerations, and Duke Energy Progress, Inc.'s determination that the proposed change does not involve a significant hazards consideration. The proposed marked-up and retyped Techircal Specrfilations (TS) pages are provided in Attachments I and 2 to the Enclosure respectvely. Marked-up TS Bases are included In Attachment 3 to the Enclosure for Information.

Approval of the proposed amendment Is requested by September 15, 2014. Once approved, the amendment shall be Implemented within 120 days.

L(Vi

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/13-0067 Page 2 of 2 The proposed change has been reviewed by the HBRSEP Plant Nuclear Safety Committee.

This letter contains no new Regulatory Commitments.

In accordance with 10 CFR 50.91(b),, a copy of this.application is being provided to the State of South Carolina. If you have any questions regarding this submittal, please contact Mr. Richard Hightower, Supervisor - Regulatory Affairs at (843) 857-1329.

I declare under penalty of perjury that the foregoing is true and correct. Executed On:

+e*-'4*6-to, 2or3 Sincerely, Sharon A. Wheeler-Peavyhouse Manager - Support Services - Nuclear SWP/sc Enclosure cc:

Ms. S. E. Jenkins, Manager, Infectious and Radioactive Waste Management Section (SC)

Mr. V. M. McCree, NRC Region II Mr. S. P. Lingam, NRC Project Manager, NRR NRC Resident Inspectors, HBRSEP Mr. A. Wilson, Attorney General (SC)

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-.RA13-0067 Page I of 7

.ENCLOSURE Evaluation of P*osed Change to TechnicaloSpeclflcAlcu.

Low Temperature Overpessure Protection (LTOP) System 10

SUMMARY

.ECRIP1nN 2.0 OEALQDESCRIPTION,

~

3.0 TECHNNICAI EVALUTIO*J

4.0 REGULATORY EVALUATION

4.1 R

ATRY E T ION 4.2 4.3 N

f

'4.4

6.0 REFERENCES

ATTACHMETS:

11-Marked-Up

'ecA SpecificaionsP P..

2-Retyped Technical Speclflctlops "Pages 3-Marked-Up Tefhical Specifiaonm Sue Peg" (For iNformon Only):

"..r

,..1."

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/13-0087 Page 2 of 7 1.0:-

SUMMARY

DESCRIPTION.,,1n.

Pursuant to 10 CFR 50.90, Duke'Energy Progress, Inc., is hereby requeting in amendment to the H. B. Robinson Steam Electric Plant Unit No. 2 (HSRSEP) renewed facility operating license CPR-23, Appendix A, Technical Spectfleattons (TS) 3.4.12, Low'Temperatuie Ovepressure Protection (LTOP) System.

The proposed amendment would modify TS SR 3.4.12.6, of TS 3.4.12,..ow Temnperature O

rp Ue PSk

,eo (LTOP) System,.with,Note that dces not requi.

t1a survWllanoe beI*poed untit 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> afte decrasing the RS cold e temp erature t'oS 30oF which it*

th temperature when LTOP operability controlled b TS 3.4A1215 credted. -, dtion, the*

FReQUENCY reqluitremnt Is modified to simply 31 ays.

29.q DETAILEIOSCI1O The-pro*se change modiie the SRSA 3412.8of ITS 3.4. f1; by Wnluin thefioigjoe a

ýNote Not required to be performed WWpI 12 to~r fter decreasing.

RCS cold leg temperature~to s 350F.

in addition, the FREQUENCY requ mnt fr. SR 3.4.12.68 fts been sim*litfid to:

'31days"'

The ropoedc ange aein accordance with NUREG-1431. Revision 3 (Rfrec 1)an darfy the channel operational test (COT) teoft requirements. The COT test Is currently required to be performed along with the plant cipoldown,6 ocess end entry Into MODE 4. This.

places a burden on the operators that could take their attention sway from other more triticaL.

transitional aclivities The proposed changes ensure that the COT testing can be performed In a reasonable time period after entry Into MODE 4 during plant cooldown when the plant activities are likely less complicated. The simplification of the FREQUENCY requirement.i also in accordance with NUREG-1431, Revision 3 and require that while in an applicable mode of operation the SR will be. performed every 31 days to ensure continued operability, This Is. the same requirement that Is currently approved In the HBRSEP TSs.

3.0 TECHNICAL EVALUATION

As described Inr the Updated Final Safety Aialysis Repod (UPSAR) Sectiont5..22, the eactor Coolant Sy~em (RCS) Is protected apanst derpreure by control and proftvcircuits such as te h!ghpssre trip and by code'rellef valves c¢nrected to the top of the rea*

ik*r. These Po*weOperoted Relief Valves (PORVO) and oode sty valved are povided to protect against predsure surges which are beyond the presur lnimig capacity of the pressurizer spray.

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/13-0087 Page 3 of 7 For ROS operation below 350°F the PORVs are utilized to protect sgarint exceeding safe pressure limits under low temperature conditions. A manual permissive switch is utilized to arm the low temperature overpressure protection (LTOP) channel (one for each PORV) beforethe RCS loop is below 350°F and capable of a solid water condition (no-steam-bubble in the -

pressurizer). Operating solid. can produce extreme pressure spikes that are not encountered when there is the cushioning effect present from a steam bubble during normal plant operation. A non-redundant temperature comparator provides an annunciator signal when the RCS loop temperature drops below 3650F.

During normal plant operation, the permissive switch is not armed and, the PORV.re no.

operable in the lowterniperature/overpressure mode. With the system not aimed,;.a reduction in temperature. below 365TF (normal cooklown procedures or abnormal conditions) causes the annunciator-to energize signaling the operator to arm the overpressure protection system via the permissive switch. Redundancy for the arming function is provided by the plant operating procedures which require arming the system prior to decreasing RCS temperature to 3509F.

When armed, the PORV$ become operable. Exceeding the setpoint with the system armed causes the PORV$ to open. The annuncato does not illuminate under normal conditions If the system was armed prior to the temperature dropping below 365WF. With the system armed below 3650F, the next energizing of the annunciator indicates the setpolnt has been, exceeded and the PORVs will open.

UFSAR Section 7.6.1 states that the PORVM are utilized to protect against exceeding safe pressure limits under low temperature conditions. Each PORV Is opened by nitrogen, with a nitrogen accumulator and Instrument air as backups. A separate nitrogen accumulator Is provided for each PORV, capable of 100 valve operating cycles. The instrumentition system for the PORVe uses temperature and pressure Inputs, Wide range temperature signals fromall throe RCS loops provide Inputs.to a lowxauctoneer, device. The low-auctioneer selects the lowest temperature to ensure using the most conservative measurement. The lowest:l"op temperature Is then utilized as input to a function generator. The output of the function generator is utilized for comparison with a plant wide-range pressure signal via a signal comparator."One wide-range.

pressure transmitter Is provided for each control channel. When the setpoint of the comparator is exceeded, the comparator's output activates a relay whose contacts activate the primary PORV solenoid and an annunciator in the Contol Room to signal the condition.

As discussed in the Bases, of TS 3.4.1-2..a PORV. Is OPERA6LE for LTQP when-its block valv is open, the PORV lift setpoint is within the limit required by th LTOP analyses and testing proves the PORV~s ability to open at this setpolnt and motive power Is available to the two PORVs and their control circuits.

To ensure PORV operability there are SRs that verify component condition, line up, setpoint, and capability to actuate.. SR 3.4.12.5 verifies the associated block valve is open for each required PORV on a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Frequency, ensuring a flow path and SR 3.4.12.7 provides an instrument channWel alibration.every 18 months to ensure that the. actuation channel is opeoble. SR 3.4.12A provides for a COT to verify the PORV lift selpoint Is wi~lin the, allowed maxdmum limits in the LTOP analyses and. as necessary, adjust Oht lift setpolnt. Since PORV.actuat could.,

depressurize.the RCS, itis not requireddudng thistesting...

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/13-00M7 Page 4 of 7 As deflned in the-HORSEP Unit No.2 TS, a COT shal be the injecon of a simulated..or.actual signal into the channel as dose to the sensor as practicable to verify the OPERABILITY of required alarm, Interlock, display, and trip functions. The COT shall Include adjustments, as necessary, of the required alarm.. interlodk, and trip setpoints so that the setlnts ar within the required range and accuracy. This definition Is further clarified in the bses-or.TS SR3.4.1 2.8 in NUREG,1431, Revision 3 and-provided in the HBRSEP Unit No,.TS 34A12 Bisesmarkup....

pages provld In Attachment 3 of this enclosure.

,Aauccessful test of the required contats) of a channel relay may be perb yt v,,:,cation of the change.of state of s singl contact of the relay This clarifies wht J an

,,.acceptable COTof a relay, This Is acceptable because all of the O*tor rmqr ts, of the relay are verifiled by other.Technical. Specifications and non-T.echnical

, ecrificaotns tsts at least once per refueling Interval with appcable, extonso.

The previpusly approvedfrequency for the SR 3.4.12.6 COT. was once.within 31 day prior to entering Modes 4, 5, and 6 when the reactor head Is on and then every 31 days.thereafter.

However, when moving frommMode 3 Into Mode 4 the. LTOP Aetting can be verified when the RCS cold log temperature reaches 3W0F which is the Mode 4 entry temperature and the LTOP minimum arming setpoint. At that point the PORV lift setpolnt can be reduced to the LTOP setting and the COT can be performed. Based on the requirements of the current approved SR 3.4.12.6 theperformance of the COT would be required totake place at the moment the-plantfls entering Mode 4. This Is a burden to the operators end potentially takes their fot=usaway from other more critic activities during that transition.

The proposed change, which Is In accordance with NUREG-1431, Revision 3, would allow performance of a COT within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after decreasing RCS cold leg temperature to % 3500F and then re-performing the COT every 31 days while in an applicable mode of operation. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> delay in performing the test provides tle opeators Mflexiblty in their priorities during the Mode 4 transition activities. In addition, the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> acceptability Isbased on the limited probability of a low temperature overpressure event during that mted time peridd. The 31 day frequency after the Initial testling, has been proven to be acceptable toensure dth LTOP continued operability based on operating experience.

Inconclution, the proposed notedoes not sgnificantly impact the safety of the plant Allowing the operator to focus on mode transition activities without requiring Immediate operability testing may enhance plant safty. With these proposed changes the HBRSEP TS will contiue to protect the health and safety of the public.

4.0 REGULATORY EVALUATION

4.1

=1111m Rac 2rifta O Per HBRSEP UFSAR Sections 3.1.1.1 and 3.1.2, the General Design Criteria (GDC) In existence at the time HBRSEP Unit No.2 was licensed (July, 1970) for operation were contained In Proposed Appendix A to 10CFR60, General eslgn Criteria. for Nucle* Powir Plants -published In the FederlIRegistl-r on July 11, 1967. (AppendXA to 10CFRSO, effective In 1971 Md subsequently amended, I somewhat different from the prDpsed 1967 criteriab

.) #RSEP was

~

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/13-0067 Page 5 of 7 evaluated with respect to the proposed 1987 GDC and the or1igal FSAR contaiuied a discussion of the critria as wellas a summary of the criteria by groups.

The followl' ng provides discussion of the affects of the propo*e change on capability of H13RSEP Unit No. 2 for continued compliance of the associated 1967 GDCs. 1967 GODC-Reactor Coolant Pressure Boundary -The LTOP is a protection system that ensures :that tile RCS boundary Is not challenged during low temperature operation. The proposed change'to the surveillance requirements does not affect operation of the LTOP system an4 does not affect the protective capabilities of the LTOP s*stem. 1967 GDC12 lnStrument and Contiol !tm

-The LTOP is a protection systemi that monitors and maintains operational parameters during low temperature operatiqn.. The propoed change to the surveillnoq requirements doqo no.I affect operation of the LTOP system and does 6

ot affect the protective monitMOIng or maintaining capabilities of the LTOP system. 1967 G C-18 Mohltorn" Fuel and Waste Storage -The LTOP is a protection system.thatensures that the RCS continues to provide adequate decay heat removal capabilities during low'tbmperature operation. The proposed change to the surveillance requirements does not affeW t operation of the LTOP system and does not affect the protective capabilities.of the LTOP system tp ensure the RCS continues to pr 9e adequate decay heat removl cal 4.2 NUREG-1431, Revision 3. Standard Technical Specification Wesighou Pats, dated June 2004, provides the guidance incorporated In t licensise amndment request The base for the guidance show that this change is acceptable and thatthere is no adverse affect on plant safety.

4.3, No 1

inft MUM Cosd2Mt Det ation Duke Energy Progress, I= Is submitting a request for an amendment to the Technical Specifications (TS), Appendix A of the Renewed Operating Lcense No. OPR-23, for H. B.

Robinson Steam Electric Plant. The proposed amendment wouid modify T$ surveillance requirement (SR) 3.4.12.6, of TS 3.4.12, Low, Tiremp"ea Qverprssure Prtection (L.tOP)

System, with a Note that does not require that survelanoe'tO beperfomied untill.12.,

u after decreasing the reactor coolant systemn (RCS) cold leg temperature to $ 350°F Which 1t temperature when LTOP operability controlled by $S 3.4,12 Is credited. In *di Wn, the FREQUENCY requirement Is modified to simply, '31 days."..

Duke Energy Progress. Inc. has evaluated whter or' not a :sgnificant hnazards car skdeiwlion Is involved with the proposed amendmentps) by focusing on t* thee stpndards set forth in 10 CFR 50.92, "Issuance of amendment," as dlscubelod.

".w..

1. Does the proposed change involve a significant Increase In the probability or consequences of an accident previously evakuated?

e. *p.. :' No.

This licnse aien metrquestproposesallowingu'p toI' 12Z hour dilay In performing the COT testing used to verify the LTOP lift setpoint following the RCS reaching the maximum temperature at which the LTOP Is required to be operable. The pressurtr power operated relief valves (PORVs) are utilized to protect against exceeding safe

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/13-0067 Page 6 of 7 pressure limits under low temperature conditions. The system is in service whenever the plant is in Modes 4, 5 and 6 with the reactor head on and the RCS temperature is at

< 350°F. The proposed change does not affect the function of the LTOP or when that function Is applicable for protection of the plant. The change only adjusts the required frequency of the initial surveillance testing after the LTOP has been put into service per plant procedures. The affected suveillance testing is not.assuhned to be an accident Initiator and hat no adverse affect on the operation of the LTOP systen.

Therefore, the proposed change does not involve a significant increase in the probability

" ir consequendes of an accident previously evaluated.

..2.z. -Does the proposed change create the possibility of a new or differentdlnd ofaccident

from any accident previously evaluated?

• Response: No.

This proposed change does not alter the design, function, or operation of, shy plant.-.

component and does not Install any newor different equipment. The malfunction of safety related equipment, assumed to be operable in the accident analyses, would not be caused as a result of the proposed technical specification change. No new failure mode has been created and no new equipment peiformance burdens are imposed.

Therefore, the proposed change does not create the-possibillty of a new or different kind of accident from any occident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The pressurizer power operated relief valves (PORV) are utilized to protect against exceeding safe pressure limits under low temperature conditions. The system is in service whenever the plant is in Modes 4, 6 and 6 with the reactor head on and the RCS temperature at S 350 OF. The proposed change does not affect the function of the LTOP or when that function Is applicable for protection of the plant The change only adjusts the required frequency of the initial surveillance testing after the LTOP has been put Into service per plant procedures. In addition, these proposed changes may enhance plant safety and reliability because the delay in the required testing will allow the operators to focus on other critical transition activities during entry Into Mode 4 operation.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above, Duke Energy Progress, Inc. concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth In 10 CFR 50.92(c),

and, accordingly, a finding of no significant hazards consideratio" is justified.

United States Nuclear Regulatory Commission Enclosure to Serial:, RNP-RAI 3-0067 Page.7 of I 4.4 Cocusions In conclusion, based on the considerations discussed above, (1) there Is reasonable assurance that the health and safety of the public will not be endangered by operation In the proposed manner, (2) such activities will be conducted In compliance with the Commission's regulations, and (3) the Issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

5.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed amendment would change a requirement with respect to Installation or use of a facility compoe.1opated within the restricted area, as defined in 10 CFR 20, or would change an inspection or sUrveilance requirement. The proposed amendment would modify technical specification surveillance requirement SR 3.4.12.6, with a Note that allows the performing of a channel operational test to be delayed up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the low temperature overpressure protection (LTOP) system In service during plant cooldown.

The proposed change has no affect on how the LTOP functions or provides proteton.

The proposed amendment does not involve (I) a significant hazards consideration; (ii) a significant change In the types or significant increases in the amounts of any effluents that may be released ofslite; or (il1) result In a significant increase In Individual or cumulative occupationa radiation exposure. Accordingly, the proposed amendment meets the eligibility criteria for categorical exclusion set forth In 10 CFR 51.22(cX9). Therefore, pursuant to 10 CFR 51.22(b), no environmental Impact statement or environmenfal assessmrent needs to be prnparpdIn connection with the Issuance of the amendment.

&.0 REFERENCES

1.

NUREG-1431, Revision 3, Standard Technical Specifications Westinghouse Plants, dated June 2004.

United States Nuclear Regulatory Commission Attachment I to Serial: RNP-RA/13-0067 2 Pages including this cover sheet ATTACHMENT 1

'MARKED-UP TECHNICAL SPECIFICATIONS PAGES' 8'

LTOP System 3.4.12

~ft iQ1I~II I AJ~~ D~flI IIQ~&1~MTL~

IEumfrtumw4~

p SURVEILLANCE FREQUENCY SR 3.4.12.6 Perform a COT on each required PORV, excluding actuation.

"q,7 recuWrd to b* OwOrm until I hU Safe decrvasiag RC cod P9tle nper~lur to 5 51 31 days SR 3.4.12.7 Perfonm CHANNEL CALIBRATION for 18 months each reqtire PORV aduaon channe HBRSEP Unk No. 2 3.4-34 HBRSEPUnit

o. 2.4-34Amndkmet W~$

United States Nuclear Regulatory Commission to Serial: RNP-RA/13-0067 2 Pages including this cover sheet I

.1 ATTACHMENT 2 RETYPED TECHNICAL SPECIFICATIONS PAGES

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)............

SURVEILLANCE FREQUENCY SR 3.4.12.6 Note-Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after decreasing RCS cold leg temperature to s 3600F.

Perform a COT on each required PORV, 31 days excluding actuation.

SR 3.4.12.7 Perform CHANNEL CALIBRATION for 18 months each required PORV actuation channel.

o,,, *.

HBRSEP Unit No. 2 3.4-34 ArwAvoid No.

United States Nuclear Regulatory Commission to Serial: RNP-RA/13-0067 3 Pages including this cover sheet 4,'

4..

4 ATTACHMENT 3

,.4 MAMKED-UP TECHNICAL SPECIFICATIONS BASES PAGES (For Information Only)

,, V

'444

LTOP Syotmn B 3.4.12 BASES

$URVIEILLANCE REQUIREWNTS Perfo'rmance of a C OT is repa~red WithIn 12 how's aftce cdecrtasln RCS cold leg temrperatuire to s' 45JF and every 31 dayý on each roquhed POV IN vterIN and, as necessary, JuMs it-,

lift setpolnt. A su~cessuI tes of

ý,theP required crontvrt(l) Ufa channelrý may 6e perfoiemd by the veý ý;tcto of the chane 0f StAteo a wlnge corfltw of thbe nýITi difý wh* is an wceqa,,e COTo'i ay.,

This Is accetable beýcaA*d of th other requirec! oontpcts ofte eel" are v~fi by

~e r I a~ta SpeciUoms aed a Y

SpecificatIons Wt at leastI t.

ae, pe retwoig lnurv with pia exwslnmm Ih

ý T wi i-theT i~,

the RC(S a nd c,

not r~u it d To Provide qfrtorsý If fýýAttjjz'fr MOOF 4 trnslti t, r n ctv,,t es a nt hos been added TndkaU 4:,VF thatOws Is not qureqU to be pw dU-11 1* hbourn a"If dcesr ý: g l

temperatre tot35o.

h 1 u

FRF!kUENCYcfond.

e unllkelihoodf atý a lOw emer The COT is recluiod to be perfomr-wfthin 12 howr after CotrI-, *s LTOP MODES tMM the OVR Se~nt td;rsedýxpeiec wIvthwI1;)

Sm-tirabTl fl t*

SR 3.412.

(contbWd) b.Once every 31 nays for a valv that is bcksd, sasdd or ICUrdIn positon.A" n

Al

ývaVeItS icgr.

fth pe@,

to"t arrangement M*s only be open to be OPERABLE. This Survelmn Is requird to be met N th.

vwfent being used to satisy the presure rW eqreenwts of the LCO 3.4.12.b.

The P01W block v"l~ mustbe vedile openevery' 7*2 hours to Wovilethe b ih oreach equhd ~OMtto Mbnfo ts funcpiwtio whn actuated. The valv must be smrasl ve~fe ope In toe ~waM contml.otf Thi Suielnce is The bloc valv 4 a remtsl con"".d moto operated

%avh* VThe poer ID fth vlv operato is n oqt rqied remved, and 1 mutual operatori is not retired 1:cked in fte kiecti positio. Thus, the bok)*v ow~ be dosed In fth even fte P0W develaps exesse" eAukage or does not doese (sftic open) aftner t

rleinan overpressur The 72,hourFrequencys cons'idere adequatein vissof 0te0 dmnsraieoobl avilable I& tie opeato In the -f room, surasvalvposiftio gc

,ta verfy thatfth PO1W blck Va"v WeaNW OWL AR 3M1112 4T>~P (uý ibJ 4 H B SE U

It Jl

~l nlII *

.*~

LoIIIII3I I

RIIIeIIIII I

ilII Illlv l I siol m HORSEP Unit No. 2 8 3.4-73 Rwhion No. 11

LTOP System B 3.4.12 BASES SURVEILLANCE 34,1-, (continued)

REQUIREMENTS t~herofe~

OnfurSl th.at SR 34-;A

-s.

re~

AoP4"bility and -has beou provewbe,44f Parfornvan of a CHANNEL CALBRATION on each required PORV ctuatn ch e IS Mrqured *vy 18 mWot to adut th0 whole chwnel so "hat it responds and the valve opens with th requred range emd accuracy to known nput.

REFERENCES I.

10 CFR 60, Appwnk G

2.

Generic Lertte 8-l.

3.

UFSAR, Chapter 5.

4.

Letter, RNPRAO-R.0141, CP&L (R. M. Krch) to NRC, "equet" for Tecohnia Spen Chwn.

Conversion to Imroved Standard Tecna Specifications Cnslnt with NUREG-1431, Stanldard Technical --

peclflcalonsWeetlngho use Plafts, Revwin I,'; Augus 30. 1996. Enclosum S.

6.

Later. NG,77-1215, CP (B. J. Furr) to NRC (R W.

Reid), "Rseatr Vessel Ovef presurization Proteftio October 31, 1977.

6.

Laeter, NG.77-1428, CPU. (E. E. Utley) to NRC (Rt W.

R*d) Reponse to Overpremse, Pvolmcion System Questios," Oecemew 16, 1977.

7.

Report, "PMrum relgalng Sy Transient Anady Re*ut" s par d by Weenatlhouw Electric Cooration fort O Weaftinhoums Owners Group on ReaorCoolan System Ovpe,-e.,to.'- *

, July 1977.

and Suppment, September 1977.

8.

1o FR 50, Secton50.46.

HSRSP Unt No 2

3.474 Rvison No.d HORSEP Unk No. 2 B83.4-74 Revision No. 0