ML18019B015

Forwards Addl Input to Final Draft Tech Specs,Consisting of Info & Justification for Each Item & marked-up Tech Spec Pages

ML18019B015
Person / Time
Site:	Harris
Issue date:	06/06/1986
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NLS-86-182, NUDOCS 8606170099
Download: ML18019B015 (50)

Text

r REGUL>> TORY INFQRNATION DISTR'IBU N SYSTEN (R IDS) 4)

ACCESSION NBR: 8606170099 DOC. DATE: 86/06/06 NOTARIZED:

NQ DOCKET I, FAG IL:50-400 Shearon Harris Nuclear Power Plant>

Unit 1>

Car ol ina

05000400, AUTH. NA1 1E AUTHOR AFFXLIATION ZXNNERNAN>S. R Carolina Power 8r Light Co.

RECIP. NANQ RECIPIENT AFFILIATION DENTON> H. R.

OFFice of Nuclear Reactor Regulation>

Director (post 8525 BUBJECT: Forwards addi input to Final draft Tech Specs> consi sting of info Zc justification for each item 8c mar1I,'ed-up Tech Spec pages. DISTRIBUTION CODE: 800}D COPIES RECEIVED: LTR ENCL SIZE: TITLE: Licensing Submittal: PBAR/FSAR Amdts i~< Related Correspondence NOTES: Application for permit renewal filed. 05000400 'E lP IENT ID CODE/NANE PWR-A EB PWR-A FOB PWR-A PD2 PD PWR-A PSB INTER NAL: ADN/LFl'18 XE FILE XE/DGAVT/GAB 21 NRR PWR-8 ADTS NRR/DHFT/HFIB 04 Rtt/DDANI/NIB EXTERNAL: 24X DNB/DBB (ANDTS) NRC PDR 02 PNL GRUEL R COP XEB LTTR ENCL } 1 1 1 1 1 0 1 1 0 1 1 1 1 0 1 1 1 1 RECIPIENT ID CODE/NANE PWR-A EICSB PWR-A PD2 LA BUCNLEY> 8 01 PWR-A RSB ELD/HDS} IE/DEPER/EPB 36 NRR BWR ADTB NRR RQE> N. L NRR/DHFT/NTB RGN2 BNL(ANDTB ONLY) LPDR 03 NSIC 05 COPXEB LTTR ENCL 2 2 1 1 2 } 1 0 1 0 i 1 1 3 3 1 1 1 TOTAL NUNBER QF COPIES REGUIRED: LTTR 32 ENCL

\\" I g HI 4H'4 4, ~ H 1 I

SNK Carotlna Power & Light Company JUN O6 1986 SERIAL: NLS-86-182 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO. 50-000 TECHNICALSPECIFICATIONS

Dear Mr. Denton:

Carolina Power R Light Company submits additional information for input into the Final Draft Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant. Attachment I provides the information as well as justification for each item. provides a marked-up copy of the affected TS pages. If you have any questions, please contact Mr. Gregg A. Sinders at (919) 836-8168. Yours very truly, SRZ/GAS/ccj (3923GAS) Attachment S.. Zim rman Man er Nuclear tcensing Section Cct Mr. B. C. Buckley (NRC) Mr. G. F. Maxwell (NRC-SHNPP) Dr. 3. Nelson Grace (NRC-RII) Mr. Travis Payne (KUDZU) Mr. Daniel F. Read (CHANGE/ELP) Wake County Public Library Mr. Wells Eddleman Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB) Dr. 3. H. Carpenter (ASLB) Mr. 3. L. Kelley (ASLB) Mr. T. S. Moore (ASLAB) Dr. R. L. Gotchy (ASLAB) Mr. H. A. Wilber (ASLAB) ,'b061700'ittrr 860606 PDR ADQCK 05000400 A PDR 411 Fayetteville Street o P. O. Box 1551 o Raleigh. N. C. 27602 Hoot

CP RL Coxnxnente S HNPP Proof and Review. Technical 8pecification s Record Number: 600 LCO Number: 3.07.13 Section Number: 4.7.13.b Comment: Comment Type: IMPROVEMENT Page Number: 3/4 7-42 CHANGE THE 18 MONTH SURVEILLANCES TO THOSE ATTACHED. Basis THIS CHANGE IS MADE TO BETTER CLARIFY THE INTENT OF THE SURVEILLANCE TO TEST THE SYSTEM FOR OPERABILITY AS WELL AS TO DETERMINE THAT NONESSENTIAL PORTIONS ARE ISOLATED.

CP Bc,L Comxnenta SHNPP Proof and Review Technical Specifications Record Number: 601 LCO Number: 3.08.01.01 &.02 Section Number: 3.8.1.1.b282.b2 Comment: Comment Type: IMPROVEMENT Page Number: 3/4 8-1 h 9 ADD A FOOTNOTE TO ITEM 3.8.1.1.bl AND 3.8.1.2.bl WHICH STATES THE FOLLOWING'AY TANK MINIMUM LEVEI REQUIREMENTS ARE NOT APPLICABLE DURING DIESEL GENERATOR OPERATION OR DAY TANK REFILL OPERATIONS. Basis THIS CHANGE IS REQUIRED DUE TO THE FACT THAT THE DAY TANK LEVEL DROPS DURING DIESEL OPERATIONS TO A LEVEL BELOW THE 2670 gal LIMIT BEFORE THE TRANSFER PUMP IS STARTED TO REFILL THE TANK. THE CURRENT WORDING OF THE SPEC DOES NOT ALLOW FOR ANY USAGE OF THE FUEL OIL IN THE TANK AND WOULD THUS REQUIRE DECLARING THE DIESELS INOPERABLE DUE TO DAY TANK LEVEL WITHIN MINUTES AFTER STARTING A DIESEL.

CPRL Coxnxnenta SHNPP Proof and Review Technical Specifications Record Number: 602 LCO Number: 3.07.12 Section Number: TABLE 3.7-6 Comment Type: ERROR Page Number: 3/4 7-41 Comment: ITEM ll CHANGE ITEM TO "lA-SA, 1B-SB, AND lC-SAB CHARGING PUMP ROOMS (el 236') ITEM 18 CHANGE THE WORD "ROOMS" TO "ROOM" Basis THE CHANGE TO ITEM 11 IS TO CORRECT A TYPOGRAPHICAL ERROR. THE SPARE CHARGING PUMP ROOM IS THE 1A-SAB PUMP ROOM THE ONLY OTHER ROOM IS EMPTY AND WILL NOT REQUIRE TEMPERATURE MONITORING. THE CHANGE TO ITEM 18 IS ALSO A TYPO. THERE IS ONLY ONE H&V EQUIPMENT ROOM ON ELEVATION 236'F THE WASTE PROCESSING BUILDING WHICH REQUIRES AREA TEMPERATURE MONITORING.

CPRL Coxnxnente SHNPP Proof and Review Technical Specificationa Record Number: 603 LCO Number: - 6.06.01 Section Number: 6.6.l.a Comment Type: IMPROVEMENT Page Number: 6-16" Comment: CHANGE THE WORDS " Section 50.73" TO "Sections 50.72 and 50.73". Basis THIS CHANGE IS MADE TO INCLUDE THE GOVERNING REQUIREMENTS OF 10 CFR 50.72 TO THE SPECIFICATION.

CP RX Coxnxnents SHNPP Proof and Review Technical Specifications Record Number: 604 LCO Number: 3.06.02.02 Section Number: 3.6.2.2.a Comment: Comment Type: ERROR Page Number: 3/4 6-12 CHANGE THE VOLUME OF THE SPRAY ADDITIVE TANK TO "BETWEEN 2736 AND 2912 GALLONS" ~ Basis THIS CHANGE IS MADE TO INCLUDE THE LATEST INFORMATION AVAILABLE TO US FORM THE A/E.

CP Bc.L Comxnents SHNPP Proof and Review Technical Syec9f9cat9ons Record Number: 605 LCO Number: 6.08.04 Section Number: 6.8.4.g Comment: Comment Type: IMPROVEMENT Page, Number: 6-19 REPLACE THE EXISTING TURBINE VALVE MAINTENANCE PROGRAM WITH THE ATTACHED. Basis THE FOLLOWING CHANGE IS MADE TO ADD A TURBINE ROTOR INSPECTION PROGRAM TO THE TECH SPECS.

i< CP Bc,X Coxnxnenta SHNPP Proof and Review Technical Specifications Record Number: 606 LCO Number:

3. 03. 02 Section Number:

TABLE 3. 3-4 Comment Type: IMPROVEMENT Page Number: 3/4 3-32 Comment: INSERT A NEW ITEM 10.b AS PER ATTACHED MARKUP AND RENUMBER THE BALANCE OF THE ESF ACTUATION SYSTEM INTERLOCK SECTION. Basis THIS CHANGE IS NECESSARY TO INCLUDE AN UPPER LIMIT TO THE P-ll SETPOINT. AS PREVIOUSLY SUBMITTED, P-11 HAD NO UPPER LIMIT. THIS IS NOT AN ACCURATE REPRESENTATION. THE P-ll RESET IS REQUIRED PRIOR TO 2014 psig.

CP%L Comxnenta SHNPP Proof and Review Technical Specifications Record Number: 607 LCO Number: B 3/4.08 Section Number: B 3/4.8 Comment: Comment Type: IMPROVEMENT Page Number: B 3/4 8-2 CHANGE THE REVISION DATE OF REGULATORY GUIDE 1.9 FROM "MARCH 10, 1971" TO "DECEMBER 1979". Basis CPEcL UPGRADED THE COMMITMENT TO REGULATORY GUIDE 1.9 FROM REVISION 0 TO REVISION 2 IN FSAR AMENDMENT 27. THIS CHANGE TO THE TECH SPECS IS FOR CONSISTENCY WITH THE FSAR.

CP 8c,I Comment a SHNPP Proof and Review Technical Specifications Record Number: 608 LCO Number: 3.06.03 Section Number: TABLE 3.6-1 Comment: Co'mment Type: IMPROVEMENT Page Number: 3/4 6-16 INSERT THE ATTACHED REPLACEMENT TABLE 3.6-1. Basis THIS CHANGE IS TO REFLECT A REVISED FSAR TABLE AND SUPPORTING ANALYSIS

CP Bc.L Comxne nte SHNPP Proof and Review Technical Specifications Record Number: 609 LCO Number: 2.02.01 Comment Type: IMPROVEMENT Page Number: 2-4,7,8 & 10 Section Number: TABLE 2.2-1 Comment: REPLACE PAGES 2-4, 2-7, 2-8 AND 2-10 WITH THE ATTACHED MARKUP PAGES. Basis THE SETPOINT STUDY PERFORMED BY WESTINGHOUSE FOR THE SHEARON HARRIS PLANT UTILIZES THE SAME BASIC METHODOLOGY AS THAT USED IN PREVIOUSLY NRC APPROVED STUDIES FOR OTHER PLANTS WITH A WESTINGHOUSE NSSS. OTHER RECENT PLANTS NOTED ARE BYRON/BRAIDWOOD, WOLF CREEK, CALLAWAY AND MILLSTONE UNIT 3. THIS METHODOLOGY IS EXPLICITLY APPROVED IN NUREG-0717 SUPPLEMENT NO. 4 SAFETY EVALUATION REPORT RELATED TO THE OPERATION OF VIRGIL C. SUMMER NUCLEAR STATION UNIT NO. 1, DOCKET 50-395, AUGUST 1982. IT SHOULD'E NOTED THAT THE WESTINGHOUSE METHODOLOGY IS CONSISTENT WITH THE FOLLOWING INDUSTRY STANDARDS AND NRC DOCUMENTS:

l. ANSI/ANS STANDARD 58.4-1979, "CRITERIA FOR TECHNICAL SPECIFICATIONS FOR NUCLEAR POWER STATION".

2. ISA STANDARD 567.04,

1982, "SETPOINTS FOR NUCLEAR SAFETY RELATED INSTRUMENTATION USED IN NUCLEAR POWER PLANTS".

3. NUREG/CR-3659 (PWL-4973), "A MATHEMATICAL MODEL FOR ASSESSING THE UNCERTAINTIES OF INSTUMENTATION MEASUREMENT FOR POWER AND FLOW OF PWR REACTORS," FEB. 1985. 4. REG GUIDE 1.105 REV. 2, INSTRUMENT SETPOINTS FOR SAFETY RELATED SYSTEMS," FEB. 1986 THE SHEARON HARRIS TECHNICAL SPECIFICATIONS FOR THE INSTRUMENT SET POINTSi TABLE 2.2-1 AND 3.3-4, REFLECT THE RECOMMENDATIONS OF TABLE 4-3 AND APPENDIX A OF "WESTINGHOUSE SETPOINT METHODOLGY FOR PROTECTION SYSTEMS$ SHEARON HARRIS (REV. 1)," AS AMENDED BY FCQL-388, DATED DECEMBER 31, 1985. THE SHNPP TECH SPEC TABLE 2.2-1 AND TABLE 3.3-4 VALUES WERE CALCULATED BY WESTINGHOUSE UTILIZING EITHER WESTINGHOUSE INHOUSE INFORMATION, DOCUMENTED SHEARON HARRIS INPUT, OR DOCUMENTED EBASCO INPUT.

CP8c.L Coznxnenta SHNPP Proof and Review Technical Specifications 'e Number: 610 LCO Number: 3.03.02 Section Number: TABLE 3.3-5 Comment Type: IMPROVEMENT Page Number: 3/4 3-34 L 35 Comment: ITEMS 2a3, 3a3 and 4a3 CHANGE THE

RESPONSE

TIME TO " IESS THAN 62(2)/72(l)". Basis THIS CHANGE IS NECESSARY BASED ON REVISIONS PROVIDED TO THE CONTAINMENT ISOLATION VALVE TABLE 3.6-1.

CP Bc.L Coxnxnent.a SHNPP Proof and Review Technical Specifications Record Number: 611 LCO Number: 3.06.02.02 Section Number: 4.6.2.2.d

Comment, Type:

ERROR Page Number: 3/4 6-12 Comment: CHANGE THE SURVEILLANCE TQ READ AS FOLLOWS: "....or equal to i7 gpm, using the RNST containing l00,000 gal ae the teat source." Basis THIS CHANGE IS TO PROVIDE THE LATEST INFORMATION AVAILABLE TO US FROM THE A/E.

+><I Coxn~ent~ S HNT'X P'z-ooZ ance Review Te eview Tech nical Syecification a Record Number: 612 LCO Number: 3.03.02 Section Number: TABLE 4.3-2 Comment Type: IMPROVEMENT Page Number: 3/4 ~-38 Comment: NQ TECH SPEC CHANGE IS NEEDED. Ba51 5 DENIAL OF THIS REQUEST AT THIS TIME WOULD HAVE A SUBSTANTIAL COST AND SCHEDULE IMPACT QN THE PLANT.'URTHER, LITTLE QR NO BENIFIT TO SAFETY WOULD BE REAL1ZED SINCE OVER 70/ (27 OUT QF 40 PER TRAIN) QF THESE RELAYS WILL BE TESTED QUARTERLY AND THE REMAINEDER WILL BE TESTED EACH REFUELING.

SENSOR ERROR ~S TRIP SETPOIRT ,'.A. N.A. TOTAL ALLOWANCE TA Z H.A. H.A. ALLOWABLE VALUE FUNCTIONAL UNIT I. Manual Reactor Trip I 2. Power Range, Neutron Flux a. High Setpoint b. Low Setpoint N.A. P f4.56] 0 [4. 56] 0 [0. 5] 0 <[111.1]X of RTP"* <[109]X of RTP"" <[25]X of RTP*" f7.5] <[27.1]X of RTP** [8. 3] 3. Power Range, Neutron Flux, f1.6] High Positive Rate <[5]X of RTP*" with <[6.3]X of RTP"" with a time constant a time constant >[2] seconds >[2] seconds TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATIQN TRIP SETPOINTS 4. Po~er

Range, Neutron Flux, f1.6]

High Negative Rate f0.5] 0 <f5]X of RTP"* with <[6.3]X of RTP*" with a time constant a time constant >[2] seconds >f2] seconds 5. Intermediate

Range, Neutron Flux f17. 0]

f8. 41] 0 <f25]X of RTP"" <[30.9]X of RTP*" 8. Overpower hT [4. 9] 9. Pressurizer Pressure-Low [5.0] 10. Pressurizer Pressure-High [7.'5] ll. Pressurizer Water Level-High f8.0]

• Loop design flow = [97,600]

gpm

• • RTP = RATED THERMAL POWER 6.

Source

Range, Neutron Flux f17.0]

7. Overtemperature hT [10. 01] 0 f6. W] fl.48] 58vk] <[10s] cps See Note 1 See Note 3 [2 18] f1.51 <[92]X of instru-ment span [2. 21] [1. 5] >[1960] psig [5. Ol] [0. 5] <[2385] psig <[1.4 x 10s] cps See Note 2 See Note 4 >[1946] psig <[2399] psig <[93.8]X of instru-ment span R'I C7

TABLE 2.2-1 Continued TABLE NOTATIONS NOTE 1: OVERTEHPERATURE AT >T (~1+ x'S} 1 (1+ x S) 1 (1 ~ ~ S) (~1~ T ) < ST~ (Kx Kg (1 + S) [T (~1~ ) - T'] + Kg(P,- P') - T~(SI)) Where: AT ~1+ x S 1 + xzS 1 ~1+ xs AT Kg K2 ~1+ t S 1 + xsS Tgp Zs 1 + rsS Measured AT by RTD Manifold, Instrumentation; t Lead-'ag compensator on measured AT; Time constants utilized in lead-lag compensator for AT, z = [83 s v, = [33 s; ss Lag compensator on measured AT; Time constants utilized in the lag compensator for AT, rq = [03 s;. Indicated AT at RATED THERMAL POWER; ~6 l.alp [0.01823l F; The function generated by the lead-lag compensator for T dynamic compensation l avg aD Time constants utilized in the lead-lag compensator for T, t = ~ s xs = [43 s; avg'verage temperature, F; Lag compensator on measured T avg'ime constant utilized in the measured T lag compensator z = [03 s. avg s <s=

TABLE 2.2-1 Continued TABLE NOTATIONS NOTE 1: (Continued) T' [5&8.8]'F (Nominal T at RATED THERMAL POMER); K3 = 0.000828/psig'l Pressurizer

pressure, psig; 2235 psig (Nominal RCS operating pressure};

NOTE 2' Laplace transform operator, s-', and f>(4I) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with gains to be -selected based on measured instrument response during plant startup tests such that: (1) For qt - qb between -[34]X and + [9.0]X, f,(hI) = 0, where qt and qb are percent RATED THERNL POMER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POMER in percent of RATED THERMAL POMER; (2) For each percent that the magnitude of qt - qb exceeds "[34]X, the hT Trip Setpoint,shall be automatically reduced by [2.02]X of its value at RATED THERMAL POMER; and (3) For each percent that the magnitude of qt - qb exceeds +[9]X, the 4T Trip Setpoint shall be automatically reduced by [1.83]X of its value at RATED THERMAL POWER. I The channel s maximum -Trip Setpoint shall not exceed its computed Trip Setpoint by more than~ 458'p AT Svwa ~ /.0 9 Q ~ 0: .0 ljP

n NOTE 3: (Continued) I C Kg TABLE 2.2-1 Continued TABLE NOTATIONS f0.00159)/ F for T > T" and Ka = 0 for T < T", As defined in Note 3., Indicated,T at RATED THERMAL POMER (Calibration temperature for AT instrumentation, < f588.8) F), S As defined in Note 1, and fq(hI) = 0 for all hI. b4I CI NOTE 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than [0ccgQ ~ i Zo ).9 QQTE,5'~< +++~K 6R~GC- ~ '~~~~ l~ ~ ><c',3 ~< ~<~<Fe.. Qg ~yegg g~g +gal S l CAW pwo Fop. Sm~VMssorz6 ls 0

TABLE 3.3"4 Continued ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS SHNPP RE/~i< t~ Qu~. ~- 1 FUNCTIONAL UNIT 9. Loss-of-Offsite Power a. 6.9 kV Emergency Bus Undervoltage Primary v }I b. 6.9 kV Emergency Bus 'ndervoltage Secondary 10. Engineered Safety Features Actuation System Interlocks N.A. N.A. N.A. N.A. TOTAL ALLOMANCE .TA 1 SENSOR ERROR ~S N.A. N.A. TRIP SETPOINT ggao ~88+ volts with a < fl.O] second time .delay. cszV > &%8%] volts with a ~kQ >gg6 second time delay (withal Safety Injection). 6/ > ~89 volts with a < f54.0] second time delay (withour Safety Injection). x +go m}.A A&I > [~] volts with a eeeesW t}me del aya~aa ct.t4 Auo IS acwlbS ciao ] volts ~ with a +gal'gggm seeesa time del ay gwitheeA Safety~"'" as'njection). 6500 > ~885 volts with a < j~~ second time 6~ delay (without Safety Injection). <sH8 }s}}tT'% asm } i WAyp~+g ALLOMABLE VALUE Dse pea s P/L~~> as d.4 Pressurizer

Pressure, P-11 PRguug t 2E'4 PWCAuk', pe-P-l/

Low"LowT, P-12 avg'eactorTrip, P-4 e.d. Steam Generator Mater Level, P-14 N.A. }r,A. N.A. N.A. <<.A, N.A. N.A. N.A. > [2000] psig dOOO PS~g > [553]'F N.A. N.A. N.A. N.A. See Item 5.b above for all Steam Generator Mater and Allowable Values. > [1986] psig golf Prig > [550.6] F N.A. Level Trip Setpoints

TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT 8. W Coincident With: Containment Spray Containment Spray Switch-over to Containment Sump a. Automatic Actuation Logic and Actuation Relays 'I b. RWST Low Low HININN TOTAL NO. CHANNELS CHANNELS OF CHANNELS TO TRIP OPERABLE APPLICABLE HODES ACTION 1, 2, 3, 4 14 See Item 7.b. above for all RMSTLow Low initiating functions and requirements. See Item 2 above for all Containment Spray initiating functions and requirements.

9. 'oss-of-Offsite Power 6.9 kV Emergency Bus"-

Undervoltage Primary 6.9 kV Emergency Bus"" Undervoltage Secondary 10. Engineered Safety Features Actuation System Interlocks 3/bus 3/bus 2/bus 2/bus 2/bus 2/bus 1, 2, 3, 4 1, 2, 3, 4 IICO 15* j9Z 15* g )+ P Q a. Pressut izer Pressure,- P-ll b Pgg~APgg~4 /~S CTAC P Low-Low T, P-12 avg'eactorTrip, P-4 2 Z 2 2 1, 2, 3 2',2,3 2 J, P, 3 1, 2, 3 20 ga 20 22 Steam Generator Water Level, P-14 See Item 5.b. above for all P-14 initiating functions and req'uirements.

SHNt f gtCPI Wg( JQN ls8s TABLE 3.3-5 PR00F AHO REMEN COPy ENGINEEREO SAFETY FEATURES

RESPONSE

TIMES INITIATION SIGNAL AND FUNCTION

RESPONSE

TIME IN SECONDS 1. Manual Initiation 2. 3. a. Safety In)ection (ECCS) b. Containment Spray c. Phase "A" Isolation d. Containment Ventilation Isolation e. Steam Line Isolation f. Reactor Trip g. Start Diesel Generator \\ Containment Pressure-High-1 a. Safety Infection (ECCS)') Reactor Trip 2) Feedwater Isolation 3) Containment Phase "A" Isolation 4) Containment Ventilation Isolation 5) Auxiliary Feedwater Motor-Driven Pumps 6) Emergency Service Water Pumps 7) Containment Fan Coolers I '.8)","; Control ~Room Isolation Pressui'i'ier."'ressure-'-L'ow I ~ a. Safety 'Infection (EGGS) N.A. N.A. N.A. N.A. N.A. N.A. N.A. P7)(1)/$ 12)(5) < f2) D)"') +sf < j:60) pz]~~~/pz]4 ~< $27) /$17)~ N.A. < (27)(1)/t 12)(5) g ~~.C 1) Reactor Trip 2) Feedwater Isolation 3) Containment Phase "A" Isolation 4) Containment Venti1ation Isolation < f2) < g7)(3) <<~Ca/ ~(6) 4,~s SHEARON HARRIS - UNIT 1 3/4 3-34

TABLE 3.3-5 Continued 586 86TINEEREQ SAFETY FEATURES

RESPONSE

TIMES INITIATINGSIGNAL AND FUNCTION

RESPONSE

TIME IN SECONOS 3. Pressurizer Pressure Low (Continued) a. Safety Injection (ECCS) (Continued) 5) Auxiliary Feedwater Motor-Orfven Pumps 6) Emergency Service Mater Pumps 7) Containment Fan Coolers 8) Control Room Isolation 4. Hain Steam Line Pressure-Low a. Safety Ingectfon (ECCS) 1) Reactor Trip < f603 -8 < f323 /C223+g < f273( )/f173(>> N.A. < f123 /f223 < f23 2) Feedwater Isolatfon 3) Containment Phase "A" Isolation 4) Contafnment Ventflatfon Isolation ,<~~(6) '~~'j>z<" 5) Auxiliary Feedwater Motor Driven Pumps 6) Emergency Service Mater Pumps 7) Contafnment Fan Coolers 8) Control Room Isolation b. Steam Line Isolation .,s, pg Contaf nme'nt* Pressure--Hf gh-3 a. Contaf nment - Spray b. Pha'se "8'-'solation 6. Containment Pressure>>-High-2 Steam Line Isolation 7. Steam Line Pressure Negativ Rate High Steam Line Isolation < f603 f323(~)/f223(+ f273(1)/I 173(&3 N.A. m~ it.S <, fka~3 /f32. 23 < f22.53 /f123 L7~~ < E73~ SHEARON HARRIS - UNIT 1 3/4 3-35

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRNENTATIOH RVEIL URHEN I M TRIP ANALOG ACTUATING CHANNEL DEVICE NSTER SLAVE CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY FUNCTIONAL UNIT CHECK CALIRRATIOH TEST TEST LOGIC TEST TEST TEST

8. Containment Spray Switch-over to Containment Sump (Continued)

MODES FOR WHICH SURVEILLANCE ~IS RE LD b. RWST LevelLow-Low Coincident with: Containment Spray

9. Loss-of-Offsite Power See Item 7.b.

above for RWST LevelLow-Low Sur veillance Requirements. See Item 2. above for Containment Spray Surveillance Requirements.

a. 6.9 kV Emergency Bus Undervoltage-Primary

b. 6.9 kV Emergency Bus Undervoltage-Secondary

10. Engineered Safety Features Actuation System Inter locks N.A.

N.A. R. N.A. N.A. H.A. H.A. N.A. N.A. 1, 2, 3, 4

a. Pressurizer

Pressure, P-ll br PlQSaRIZEA jggggAIgg P<y-P )/

Os. Low-l.ow T, P-12 db. Reactor Trip, P-4 eW. Steam Generator Water Level, P-14 N.A. al,A N.A. H.A. See Item R R N.A. 5.b; above ~ ~ ~ H N.A., N.A. e.A.. N.A. H N.A..'-; N.A. N;A. R N.A. for P-14 Surveillance Requirements. K H.A. 4.A. N.A. H.A. H.A. N.A. H.A. 1, 2, 3 z, d,3 1, 2, 3 1, 2, 3

CONTAINMENT SYSTEMS SPRAY ADDITIVE SYSTEM SHMQ PA00F Atm PEIgEI I;spy LIMITING CONDITION FOR OPERATION 3.6.2.2 The Spray Additive System shall be OPERABLE with: 2738 ~i~ a. A spray additive tank containing a volume of between [~3 and gy/g ~y~ I.~) gallons~ tb fit] df~3by dgh hCH 9(2'?n b. Two spray additive eductors each capable of adding NaOH solution from the chemical additive tank to a Containment Spray System pump flow. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION:. Nth the Spray Additive System inoperable, restore the system to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours; restore the Spray Additive System to OPERABLE status within the next 48 hours or be in COLO .SHUTOOMN within the following 30 hours. ('URVEILLANCERE UIREMENTS 4.6.2.2 The Spray Additive System shall be demonstrated OPERABLE: ae At least once per.31 days by verifying that each valve (manual, power operated, or automatic) in the flow path that is not locked,

sealed, or otherwise secured in position, is in its correct position; b.

At least once per 6 months by: c d. 1. Verifying the contained solution volume in the tank, and 2.. Verifying the concentration of the NaOH solution by chemical analysis. At,,least once per 18 months during shutdown, by verifying that each autamatic valve in the flow path actuates to its correct position on a ccntalnment spray er centalnment lsalatlcn phase A as appllcableI e~d ~i+ Otgmsal At leist once per 5 years by verifying each eductor flow rate is greater than or equal to gpm, using the RWST as the test source and . eeq,fa)nlgg a+ 18'.Q lOCb) OOO )g(cutlet esp SHEARON HARRIS - UNIT 1 3/4 6-12

PENETRATION NO. VALVE NO. CP&L ~(EBASCO TABLE 3.6-1 CONTAINMENT ISOLATION VALVES FUNCTION SHNPP REVIStog JUN I86 MAXIMUM ISOLATION APPLICABLE 1. PHASE A ISOLATION 1MS-25 (MS-V122) 1MS-27 (MS-V124) 1MS-29 (MS-V126) -1CS-7 (CS-V511) MAIN STM LOOP A PRIMARY SAMPLING PANEL MAIN STM LOOP B PRIMARY SAMPLING PANEL MAIN STM LOOP C PRIMARY SAMPLING PANEL .CVCS NORMAL LTDN ISOL <60 1~ 2,'6 <60 1,2,6'60 1,2,'6 ~ 10...,:N/A,, 1CS-8 (CS-V512) CVCS NORMAL'LTDN ISOL 10 N/A 1CS-9 (CS-V513) 1CS-11 (CS-V518) CVCS NORMAL LTDN ISOL I'VCS NORMAL LTDN ISOL 10 N/A 10 'N/A 33 33 37 38 40 42 1CS-470 (CS-V516) 1CS&72 (CS-V517) 1SP-209 (SP-V408) 1SP-208 (SP-V409) 1CC-176 (CC-V172) 1CC-202 (CC-V182) 1RC>>161 (RC-D525) 1ED-121 (WL-L600) CVCS SEAL VZR RETURN & EXCESS LTDN CVCS SEAL WTR RETURN & EXCESS LTDN GAS RETURN FROM P.A.S.S. SKID 82 GAS RETURN FROM P.A.S.S. SKID 82 CCW TO RCDT & EXCESS LTDN HEAT EXCH. CCW FROM RCDT & EXCESS LTDN HEAT EXCH. REACTOR MAKEUP WTR TO PRT RCDT PUMP DISCH. 10 10 5 10 10 C60 10 N/A N/A 3p i 1,6,2 1,6,2

TABLE 3,6 I (Conttd) CONTAINMENT ISOLATION VALVES SHNpp >tptma ~ JUN mS6 42 IED-125 (WL-D650) VALVE NO. PENETRATION CPSL NO. ~(EEASCO FUNCTION RCDT PUMP DISCH MAXIMUM ISOLATION TIME SEC 10 APPLICABLE NOTES 2 74 74 76A 76B 76B 77A 7.7B. 77B 77C lED-94 (MD-V36) IED-95 (MD-V77) ISI-179 (SI-V554) ISI-263 (SI-V555) ISI-264 (SI<<V550) ISI-287 (SI-V530) IRC-141 (RC-D528) IRC-144 (RC-D529) LED-164 (WG-D590) CTMT SUMP PUMP DISCH CTMT SUMP PUMP DISCH ACCUMULATOR FILL FROM RWST ACCUMULATOR TO RWST ACCUMULATOR TO RWST N2 TO ACCUMULATORS PRT N2 CONNECTION PRT N2 CONNECTION RCDT - H SUPPLY 2 c60 <60 10 10 10 10 10 10 10 2.3 2t3 2t3 2t3 2 77C 78A 78B IED-161 RCDT - H2 SUPPLY (WG-D291) ISP-948 ,RCS SAMPLE (SP.-,'IIL) f ISP.-949."-', RCS SAMPLE ,, (SP-V23) n ISP-40 PRESSURIZER LIQ SAMPLE (SP-Vll) 10 <60 (60 460 2

PENETRATION NO. 78B 78C 78C 78D 78D 78D 78D VALVE NO. CP&L ~EBASCO 1SP-41 (SP-V12) asp-59 (SP-V1) 1SP-60 (SP-V2) 1SP-78 (SP-V113) 1SP-81 (SP-V114) 1SP-84 (Sp-vaa5) 1SP-85 (SP-V116) TABLE 3.6-1 (Cont'd) CONTAINMENT ISOLATION VALVES FUNCTION PRESSURIZER LIQ SAMPLE PRESSURIZER STEAM SAMPLE PRESSURIZER STEAM SAMPLE ACCUMULATOR SAMPLE ACCUMULATOR SAMPLE ACCUMULATOR SAMPLE ACCUMULATOR SAMPLE SHNP P P~l8'I(. M JUN $86 MAXIMUM ISOLATION APPLICABLE 460 460 460 4'60 <60 460 460 80 IIA-216 (IA-V192) INSTRUMENT AIR SUPPLY 460 N/A 88 1SP-201 LIQUID SAMPLE RETURN FROM (sp-v406), pAss sKID 81 88 91 91 92 105 -1SP-200 (SP-V407) 1SW-240 (SW-B89) 1SW-242 (SW-B90), 1SW-231 (SW-B88). 1FP-347 (FP-Bl) LIQUID SAMPLE RETURN FROM PASS SKID da SERVICE WATER FROM NNS FAN COILS SERVICE WATER FROM NNS FAN COILS SERVICE WATER TO NNS FAN COILS FIRE WATER SPRINKLER SUPPLY 460 <60 460 460

PENETRATION NO. 108 VALVE NO. CPSL ~(EBASCO lAF-155 (AF-V162) TABLE 3.6-1 (Conr.$ d) CONTAINMENT ISOLATION VALVES FUNCTION AUX. F.W. TO S/G A (HYDRAZINE) SHNPP pal/(8)+pl JUN $86 MAXIMtJM ISOLATION APPLICABLE 10 1,2,6 108 109 1AF-153 (AF-V163} lAF-159 (A'F-V164) AUX. F.W. TO S/G A (AMMONIA) AUX. F.W. TO S/G B. (HYDRAZINE) 10 10 '1,2,6 '1$ 2.6 109 110 lAF-157 (AF-V165) lAP-163 (AP-V166') AUX. F.W. TO S/G B (AMMONIA) AUX. P.W. TO S/G C (HYDRAZINE) 10 1;2,6 10 ".1;2;6 110 73B 73B 86A 86A 86B 86B lAP-161 (AP-V167) 1SP-12 (SP-V300) 1SP-915 (SP-V348) 1SP-941 (SP-V301} 1SP-917 (SP-V349) 1SP-42 (SP-V308) 1SP-919 (SP-V314)'SP-62 (SP-V309) 1SP-/fan (SP-V315) AUX. F.W. TO S/G C (AMMONIA RAD MONITOR 6 H2 ANALYZER RAD MONITOR 6 H2 ANALYZER RAD MONITOR 6 H2 ANALYZER RAD MONITOR 6 H2 ANALYZER 'YDROGEN ANALYZER HYDROGEN ANALYZER HYDROGEN ANALYZER HYDROGEN ANALYZER 10 460 e60 4'0 a60 460 460 +60 460 -;;1;"'2 $ 6: "2 .2, 2 $ 3' $ 3 2$ 3 2 $ 3

TABLE 3.6-1 (Cont'd} CONTAINMENT ISOLATION VALVES SHNPP Q~ltgl&kl JUN 586 PENETRATION NO. VALVE NO. CP&L ~(EBASCO FUNCTION MAXIMUM ISOLATION TIME SEC APPLICABLE NOTES 2. PHASE B ISOLATION 1CC-208 (CC-V170) CCW TO RCP 10 N/A 36 39 39. 1CC-297 (CC-V184) 1CC-299 (CC>>V183) 'iCC-249 (CC-V191) 1CC-251 (CC<<V190) CCW FROM RCP CCW FROM RCP CCW FROM RCP THERMAL BARRIERS CCW FROM RCP THEmL BARRIERS 10 10 10 10 N/A N/A N/A N/A 3. SAFETY INJECTION'ACTUATION 1CS-238 CVCS NORMAL CHARGING (CS-V610) 10 N/A 51 52 53 54 55 56 1BD>>ll (BD-Vll) 1BD-30 (BD-V15) 1BD-49 (BD-V19) 1SP-217 (SP-V120) C 1SP-222 (SP-V121) 1SP<<'27 (SP-V122) S/G A BLOWDOWN S/G B BLOWDOWN S/G C BLOWDOWN S/G A SAMPLE S/G B SAMPLE S/GC SAMPLE C60 460

4. 60

<60 c60 4 60 1,2,6 1;2,6. 1.2,6 1',2,6 1,2,6 1,2,6 4. CONTAINMENT VENTILATION ISOLATION 57 CP-Bl (CP-Bl) CP-B3 (CP-B3) CONTAINMENT ATMOSPHERE PURGE MAKEUP (8") CONTAINMENT ATMOSPHERE PURGE MAKEUP (42"} 3.5 15 2 $ 5

TABLE 3.6-1 (Cont t d) CONTAINMENT ISOLATION VALVES SHNPP PPvlc't~"'UN $86 PENETRATION NO. 57 58 58 58 58 59 98 VALVE NO. CP&L ~EBASCO CP-B4 (CP-B4) CP-B2 (CP-B2) CP-B 7 (CP-B 7) CP-B5 (CP-B5) CP-B8 (CP-B8) CP-B6 (CP-B6) CB-Bl (CB-Bl) CB-B2 (CB-B2) FUNCTION CONTAINMENT ATMOSPHERE PURGE MAKEUP (42") CONTAINMENT ATMOSPHERE PURGE & MAKEUP (8") CONTAINMENT ATMOSPHERE PURGE EXHAUST (42") CONTAINMENT ATMOSPHERE PURGE EXHAUST (8") CONTAINMENT ATMOSPHERE PURGE EXHAUST (42") CONTAINMENT ATMOSPHERE PURGE EXHAUST (8") CONTAINMENT VACUUM RELIEF CONTAINMENT VACUUM RELIEF MAXIMUM ISOLATION TIME SEC 15 3.'5 3.5 15 3.5 APPLICABLE NOTES 2t5 5 2B5 5. CONTAINKTNT SPRAY ACTUATION 1CT-50 CONTAINMENT SPRAY (CT-V21) N/A 3 24 1CT-88 (CT-V43) CONTAINMENT SPRAY N/A 3 ',' ~ MAIN STEAM LINE ISOLATION 3 1MS-80 MSIV (S/G A) (MS-Vl-)'>4 1MS-81 (MS-Fl) 1MS-231 (MS-V59) 1MS-82 (MS-V2) MSIV BYPASS MS DRAIN TO CONDENSER MSIV (S/G B) 10 460 1,2,3,6 1,2,6 1,4

PENETRATION NO. VALVE NO. CP&L ~EBAS CO TABLE 3'-1 (Cput.tg CONTAINMENT ISOLATION VALVES FUNCTION MAXIMUM ISOLATION APPLICABLE lHS-83 (MS-F2) 1MS-266 (HS-V60) lMS-84 (MS-V3) lHS-85 (HS-F3) 1MS-301' (MS-V61) HSIV BYPASS MS DRAIN TO CONDENSER . MSIV (S/G C) MSIV BYPASS MS DRAIN TO CONDENSER 10 c 60 10 460 1~2~3~6 1,2,6 1,3 1,2,3,6 1~2,6 7. MAIN'EEDWATER 'LINE'SOLATION 1FW-159 (FW-V26) 1FW<<307. (FW-V123) 1FW-165 (FW-V89) . 1FW-163 (FW-V90) 1FW-277 (FW-V27) .1FW-'319 (FW-V124). Cg 'y( L/f 1FW-279'FW-V91)',". L. 1FW-281 (FW-V92) 1FW-217 (FW-V28) 1FW-313 (FW-V125) FEEDWATER LOOP A FEEDWATER LOOP A BYPASS VALVE FEEDWATER LOOP A (HYDRAZINE) FEEDWATER LOOP A (AMMONIA) FEEDWATER LOOP B FEEDWATER LOOP B BYPASS VALVE 'll ~ ' FEEDWATER LOOP B (AMMONIA) FEEDWATER LOOP B (HYDRAZINE) FEEDWATER LOOP C FEEDWATER LOOP C BYPASS VALVE 10 (60 <60 10 c 60 < 60 10 1,2,6 1,2,6 1,2,6 1,2,6 1,2,6 lj2,6 1,2,6 1,2,6 1,2,6 1,2,6

PENETRATION NO. VALVE NO. CP&L ~NBA>CO TABLE 3.6-1 (Cont>d) CONTAINMENT ISOLATION VALVES FUNCTION SHNPP FtP/tc'.l~>> JUN 886 MAXIMUM ISOLATION APPLICABLE 108 109 110 1FW-223 (FW-V93) 1FW-221 (PW-V94) 1AF-64 (AF-V156) IAF-102 (AP-Vl'57) lAF-81 (AF-V158) FEEDWATER LOOP C (AMMONIA) FEEDWATER LOOP C (HYDRAZINE) AUXILIARYFEEDWATER A PREHEATER BYPASS AUXILIARYFEEDWATER B PREHEATER BYPASS AUXILIARYFEEDWATER C PREHEATER BYPASS c60 <60 10 10 10 1>2,6 1,2,6 1,2,6 1,2,6 1;2,'6 8 AUXILIARY'EEDQATER 'SOLATION 108 108 109 lAP-55 (AF-V1O) 1AF-137 (AP-V116) lAP-93 (AF-V19) AUXILIARYPEEDWATER TO S/G A AUXILIARYFEEDWATER TO S/G A AUXILIARYPEEDWATER TO S/G B 24 24 1,6 1,6 1,.6 109 lAP-143 AUXILIARYPEEDWATER TO S/G B (AF-Vl17) 1,6 .110 LQ'-74 (AF-V23) AUXILIARYFEEDWATER TO S/G C '24 1,6 110 1AP-149.,;;:,.'*' 'AUXILIARYPEEDWATER TO S/G C (AP-V1.18) L 9. REMOTE MANUAL'VALVES ~< ~ ~ pt 1MS-58 S/G PORV (S/G A) (MS-P18) 24 N/A 1,6 1,2,3,6 1MS-60 (MS-P19) 1MS-62 (MS-P20) S/G PORV (S/G B) S/G PORV (S/G C) N/A N/A 1,2,3,6 1,2,3,6

TABLE 3.6-1 (Cput:Ed) CONTAINMENT ISOLATION VALVES SHNPP p~iipfr.>> JUN )986 PENETRATION NO. 10 VALVE NO. CPSL ~(EBASCO 1CS-341 (CS-V522) 1CS-382 (CS-V523) 1CS-423 (CS-V524) FUNCTION CVCS SEAL WATER TO RCP A CVCS SEAL WATER TO RCP B CVCS SEAL WATER TO'CP C MAXIMUM ISOLATION N/A N/A N/A APPLICABLE NOTES N/A N/A N/A 13 14 15 16 18 20 21 22 26 27 28 29 30 1SI-340 (SI-'579) 1SI-341 (SX-V578) lRH-2 (RH-V503) 1RH-40 (RH-V501) 1SI-359 (SI-V587) 1SI-107 (SX-V500) 1SX-86 (SI-V501) 1SI-52 (SX-V502) 1SW>>92 (SW-B46)- 1SW-9I. (SW-B45) 'SW>>225 (SW-B52) 1SW-227 (SW-B51) 1SW-97 (SW-B47) 1SW-109 (SW-B49) SI-.LOW HEAD TO COLD LEGS SI-LOW HEAD TO COLD LEGS RHR PUMP SUCTION (TRAIN A) RHR PUMP SUCTION (TRAIN B) SI LOW HEAD TO HOT LEG SI HIGH HEAD TO HOT LEG SI HIGH HEAD TO HOT LEG'I HIGH HEAD TO COLD LEG SERVICE WATER TO FAN COOLER AH-3 SERVICE WATER TO FAN COOLER AH-2 SERVICE WATER TO FAN COOLER AH-1 SERVICE WATER TO FAN COOLER AH-4 SERVICE WATER FROM FAN COOLER AH-3 SERVICE WATER FROM FAN COOLER AH-2 N/A N/A, N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 1,3 1,3 ,.3 1,6 1B6 1,6 1,6 1,6 1,6

PENETRATION NO. VALVE NO. CPSL ~(EBAS CO TABLE 3.6-1 (Cont'd} CONTAINMENT ISOLATION VALVES FUNCTION SHNPP RFVIQI~"~ JUN $86 MAXIMUM ISOLATION APPLICABLE 31 32 1'7 17 2, 63 1SW-98 (SW-B48) 1SW-110 (SW<<B50) 1SI-3 (SI-V505.)'SI-4 (SI-V506) 1MS-70 (MS-V8) 1MS-72 (MS-V9) CM-B5 (CM-B5) SERVICE WATER FROM FAN COOLER AH-1 SERVICE WATER FROM FAN COOLER AH-4 SI TO HIGH HEAD COLD LEG SI TO HIGH HEAD COLD LEG MAIN STEAM B TO AUXILIARYF.W. TURBINE MAIN STEAM C TO AUX. F.W. TURBINE . H2 PURGE EXHAUST N/A N/A N/A N/A N/A N/A N/A 1,6 1,6 1 3,6 1;,3,6 10. 'MANUAL'ALVES 17 34 41 42 1SI-43 (SI-V30) 1LT-6 (LT-V2) 1SA-80 (SA-V14) 1ED-119 (WL-D651), SI-HIGH HEAD TO COLD LEGS ILRT ROTOMETER (LOCKED CLOSED) SERVICE AIR (LOCKED CLOSED) .': RCDT PUMP DISCH BYPASS N/A N/A N/A N/A 1r3 2 $ 3 2'3 2$ 3 44 1SF-145-, REFUELING CAVITY CLEANUP (SF-D164) (LOCKED CLOSED) N/A 2>>3 44 45 1SF-144 (SF-D165) 1SF-118 (SF-D25) 1SF-119 (SF-D26) REFUELING CAVITY CLEANUP (LOCKED CLOSED) REFUELING CAVITY CLEANUP (LOCKED CLOSED) REFUELING CAVITY CLEANUP (LOCKED CLOSED) N/A N/A N/A 2/3 2 ' 2 3

TABLE 3.6-1 (Cput'd) CONTAINMENT ISOLATION VALVES SHNpp R~)a~g~l JUN )986 PENETRATION NO. VALVE NO. CP&L ~(EBASCO FUNCTION MAXIMUM ISOLATION TIME SEC APPLICABLE NOTES 79 62 63 90 108 109 110 CM-B6 (CM-B6) 1FP-355 (FP-V44) 1LT-10 (LT-'V4) CM-B4 (CM-B4) 1DW-63 (DW>>V120) 1LT-'4 (LT-V1) - lAF-174 (AF-V189) 1AF-173 (AF-V190) lAF-175 (AF-V191) H2 PURGE MAKEUP (LOCKED CLOSED) FIRE WATER STANDPIPE SUPPLY ILRT (LOCKED CLOSED) H2 PURGE EXHAUST (LOCKED CLOSED) .DEMIN WATER SUPPLY (LOCKED CLOSED) ILRT (LOCKED CLOSED) WET LAY-UP TO STM GEN A AF HEADER WET LAY-UP TO STM GEN. B AF HEADER WET LAY-UP TO STM GEN. C AF HEADER N/A N/A N/A N/A. N/A N/A N/A N/A N/A 2B3 2B3 2B 3 2's 3 1B2B6 1,2,6 lp 2,6 11.. CHECK'VALVES 1CS-477 (CS-V515) CVCS NORMAL CHARGING N'/A N/A 23 24 35 36 1CS-4'71 '(CS-V67). 1CT-53' (CT-V27) 1CT>>91 (CT-V51) 1CC-211 (CC-V171) lCC-298 (CC-V51) CVCS SEAL WATER RETURN & EXCESS LETDOWN CONTAINMENT SPRAY TRAIN A CONTAINMENT SPRAY TRAIN B CCW TO RCP CCW FROM RCP N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A

PENETRATION NO. VALVE NO. CP&L ~EBASCO TABLE 3.6-1 (Cont'd) CONTAINMENT ISOLATION VALVES FUNCTION SHNPP REVELS'OM JUN I86 MAXIMUM ISOLATION APPLICABLE 39 40 41 59 61 76A 77A 79 80 90 ZCC-250 (CC-vso) 1RC-164 (RC-V525) 1SA-82 (SA-V15) CB-Vl (CB-Vl) CM-Vl (CM-Vl} 1SI-182 (Sr-V15P) 1SI-290 (SI-V188) 1FP-357 (FP-V48) lAI-220 (AI-V33) 1DW-65 (DW-V121) CCW FROM RCP THERMAL BARRIER DEMIN WATER TO PRT SERVICE AIR CONTAINMENT VACUUM RELIEF H2 PURGE MAKEUP ACCUMULATORY FILL FROM RWST N2 TO ACCUMULATORS FIRE WATER STANDPIPE SUPPLY INSTRUMENT AIR SUPPLY DEMIN WATER SUPPLY N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A P/A N/A 92 94A 1SW-233 SERVICE WATER TO NNS FAN COILS (SW-V142) . EXCESS FLOW CHECK VALVE FOR'TMT VACUUM RELIEF SENSING N/A N/A N/A 94B 94C 95A 95B (B) - .."~'; (B) (B) (B) EXCESS FLOW CHECK VALVE FOR CTMT VACUUM RELIEF SENSING EXCESS FLOW CHECK VALVE FOR CTMT VACUUM RELIEF SENSING EXCESS FLOW CHECK VALVE FOR CTMT VACUUM RELIEF SENSING EXCESS FLOW CHECK VALVE FOR CTMT VACUUM RELIEF SENSING N/A N/A N/A N/A

PENETRATION NO. VALVE NO. CP6L ~BBABCO TABLE 3. 6-1 (Con t') CONTAINMENT ISOLATION VALVES FUNCTION SHNPP pP/la)At i ~gUN $86 MAXIMUM ISOLATION APPLICABLE 98 105 CB-V2 (CB-V2) 1FP-349 'FP-V46)'ONTAINMENT VACUUM RELIEF FIRE WATER SPRINKLER SUPPLY N/A N/A N/A N/A 12', RELIEF VALVES 1CS-.10 (CS-R500) CVCS NORMAL LETDOWN N/A N/A 15 16 30 31 32 1RH-7 (RH-R501) 1RH-45 (RH-R500) 1SW-95 (SW-Rl) 1SW-107 (SW-R3) 1SW-96 (SW-R2) 1SW-108 (SW-R4) RHR SUCTION PROM HOT LEG RHR SUCTION FROM HOT LEG SERVICE WATER FROM PAN COOLER AH-3 SERVICE WATER FROM FAN COOLER AH-2 SERVICE WATER FROM RAN COOLER AH-1 SERVICE WATER FROM PAN COOLER AH-4 N/A N/A N/A N/A N/A N/A

TABLE 3.6-1 (Cont'd) 8HNF p RPVf8]~~i JUN gag (1) Not sub)ect to Type C leakage tests (2) The provisions of Specification 3.0.4 are not applicable (3) This valve may be opened on an intermittent basis under administrative control. (4). The Main Steam Isolation Valves (MSIV's) are included for table ~ completeness. The requirements of Specification 3.6.3 do not apply because the. OPERABILITY requirements for the MSIV's are governed by Specification 3.7.1.5. (5) May be opened only as permitted by Specification 3.6.1.7. (6) For this valve, -the closed system in which.it is located is considered to be an OPERABLE isolation valve for purposes of compliance with the ACTION statement.

TABLE 3. 7-6 AREA TEMPERATURE MONITORING saaoF Axo aaoEI goI y AREA REACTOR AUXILIARYBUILDING ~ 8r HAXIHUH TEMPfFEATURE LIMIT 4F 1. Control Room Envelope, (El 305') 2. Process IKC, Room (El 305') 3. Rod Control Cabfnets Area (El 305') 4. AM Battery Rooms (El 286') 5. AS Swftchgear Roams (El 286'). 6. Mafn Steam, Feedwater Pfpe Tunnel (El 286' 261') 7. SALSB Electrfcal Penetratfon Areas (El 236') 8. Area wfth HCC IA35HSA and IB35SB 9. HVAC Chfllers, Auxflfary Rf Pfpfng 4 Valve Area (El 236') 10. CCW Pumps, CCW Hx, Auxflfary FW Pumps Area (El 236') u. IA-SA, IB-'SB,+IC-SAB~~~ Chargfng Pump Rooms (El 236') AALU 12. Servfce Water Booster Pump 1B-SB 13. Hechanfcal and Electrfcal Penetratfon Areas (El 236') 14. Contafnment Spray Addftfve Tank, and NN Equfpment Area tEl 216') 15. Trafns ASS Cantafnment Spray

Pump, RHR Pump, NLV Equfpment Areas FUEL HANDLING BUILDING 16.

Trafns AS Emergency Exhaust System Areas (El 261') 17. Fuel Pool Coolfng Pump and Heat Exchanger Area (El 236') WASTE PROCESSING BUILDING 1S. 66V Kqu<pnont Room] (Kl 236') MISCELLANEOUS I9,. Condensate'Storage Tank Area (El 261') 20. Ofesel fuel Of 1 Storage Bufldfng (El 242') 2L ,Emi'rgency Servfce Water Electrfcal Equfpment Room 22:."-'Emergency 'Se&fce Water Pump Roam 23.: =..IA';SA~Ci 18-SB"- Exhaust Sflencer Raoms (El 292')

24. " IA-;.SA 4 IB-SB'8N Equfpment Rooms (El 292')

25. IA-SA 4 IB-SB %V Equfpment Rooms (El 280') 26. IA-SA 4 IB-SB Electrfcal Rooms (El 261') 27. IA-SA 8 IB-SB Dfesel Generator Rooms (El 261') 85 85 104 85 90 116 104 104. 104 104 '04 '04 104 104. 104 104 I22 122 104 I22 122 122 IIO 104 120 ~ I ~ 8 ~ lg SHEARON HARRIS - UNIT I 3(4 ?-41

PLANT SYSTEMS SHXPP ~ REVISION JUN $86 PROOF A'IO ABlB t,'OPy 3/4.7.13 ESSENTIAL SERVICES CHILLED WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.13 At least two independent Essential Services Chilled Mater System loops shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: With only one Essential Services Chilled Water System loop OPERABLE, restore -t least two loops to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE RE UIREMENTS 4.7.13 The Essential Services Chilled Mater System shall be demonstrated OPERABLE by: a. IPerformance of surveillances as required by. Specification 4.0.5, and b. At least once per 18 months by demonstrating that, / &><SSSJ7/AL WRnOAS o> THC SVSR' /RE4'l ld l<8<<Y /gygp~y pp>g g~<<ip7. >+ g gyp'~ /A~dllod ~M87l& s'rwAac,'~a, ~H< KSSZusihc, gage>cry 6/) <t0 AVvn8ricRc.iy oA g ggpz7p'ArZclzoJ Acza+W>> SHEARON HARRIS - UNIT 1 3/4 7-42

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8. 1 A.C. SOURCES SHNpp RFV~SNO~< QUID 198'ROOF Atl0 RB)D'k COPY OPERATING LIHITING CONOITION FOR OPERATION Two physically independent circuits between the offsite transmission network and the onsite Class 1f distribution system, and b. Two separate and independent diesel generators, each with: 1. A separate day tank'containing a minimum of 2670 gallons of fuel, which is equivalent to [&~Xindicated level, gpggArfc gt.S'. R mafn fuel oll storage tank conte<ning a m$ nfmum of <oo,~ 4&pQQG gallons of fuel~ 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE: a. 3. A separate fuel oil transfer pump. APPLICABILITY: HOGES 1, 2, 3 and 4. ACTION: pg,feted IHf ~ C4~$ l4+ ~ts gc,md/ c a. Nth one offsfte circuit of 3.8.1.1.a inoperable, demonstrate the OPERABILITY of the remafnfng A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour,and at least once per 8 hours thereafter. If either emergency diesel generator EOG has not been successfully tested wfthfn the~ 24 hour emonstra OPERABILITY by performfng Surveillance Requirement 4.8.1.1.2.a.4 separately for each such EDG within 24 hours. Restore the offsite cfrcuft to OPERABLE status within 72 hours or be fn at least HOT STANOBY wftfHn the next 6 hours and COLD SHUTDOWN within the fol-lowfng 30~hours. b."', Mfth;one*diesel generator of 3.8.1. 1.b inoperable, demonstrate the ,OPERABILITY of, the A.C. offsite sources by performing Surveillance 'Requirement 4;8.1.1. 1.a wfthin 1 hour and at least once per 8 hours

thereafter;;and if the EDG became inoperable due to any cause other

",than preplantned preventative maintenance or testing, demonstrate th'e OPERABILITY of the remafnfng OPERABLE EGG performin Surveil-lance Requirement 4.8.1.1.2.a.4 within 24 hours", restore the diesel generato~ to OPERABLE status within 72 hours or be at least HOT STANOBY within the next 6 hours and fn COLD SHUTDOWN within the following 30 hours. ~ 881 7j~d. ~Ju/md~ ~>E'L Z u Rr b < R~@u/zr~zum Mz u/Jr IPPJJCJJQLj, ggrgJug +J pffft ggp)$~7+g Qpfg+7 Jdld "This test is required to be completed regardless of when the inoperable EDG is restored to OPERABILITY. M The dmccf ckelf <<ce ac me<<dcacd i<<~cceble ~" ocf~r,+cc pacdac cd ce sHEARQH tfARRIs - untl P s/4 8-1

ELECTRICAL POWER SYSTEHS A.C. SOURCES SHNPP REyiStON JUN IS86 PROOF AHO RBl g ggpy SHUTOQWN LIMITING CONOITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE: a. One circuit between the offsite transmission network and the onsite Class 1E distribution system, and b. One diesel generator with: l. Gay tank containing a minimum volume of t:2670] gallons of fuel, which fs equivalent to their>> jX indicated level, ~ 2. A main fuel oil storage tank containing a minimum volume of ~~ ~~%9 gallons of fuel, ..Lw~ and 3. A fuel oil transfer pump. APPLICABILITY: HOOES 5 and 6. ACTION: Nth less than the above minimize required A.C. electrical power sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel,.or crane operation with loads over irradiated fuel and within 8 hours, depressurize and vent the Reactor Coolant System through a vent of greater than or equal to 2.45 square inches. In addition, when in NOE 5 with the reactor coolant loops not filled, or in MOOE 6 with the ~ater level less than 23 feet above the reactor vessel

flange, immediately initiate corrective action to restore the required sources to OPERABLE status as soon as possible.

SURYEILLANCE"'RE UIREHENTS 4.8.1.2',,Thi'above'equired A.C. electrical power sources shall be demonstrated OPERABLE by',the p'erfori4nce of each of the requirements of Specifications 4.8.1.1.1 and 4.8.1.1.2. 78 PaX 7au~ LW~C. Reguieens.erg gee ~o~ ~~~Cic~er Z Ouaiac DiZZZ~ 4f>C~~~< oezgwd < >q u>> ~+~+ g~>><< g~~~~~ SHEARON HARRIS " UNIT 1 3/4 8-9

ADMINISTRATIVECONTROLS REPORTABLE EVENT ACTION Continued I/' -'f JUN 85 PROOF AND BBH IlGPY a ~ b. The Commission shall be notified and a report submitted pursuant to the requirements of Sectiona50.75ffto 10 CFR Part 50, and mo <o.73 Each REPORTABLE EVENT shall be reviewed by the

PNSC, and the results of this review shall be submitted to the Manager-Corporate Nuclear Safety Section and the Vice President-Harris Nuclear Project.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour. The Vice President-Harris Nuclear Project and the Manager-Corporate Nuclea'r Safety Section shall be notified within 24 hours; b. A Safety Limit Violation Report shall be prepared. 'he report shall be reviewed by the PNSC.'his report shall describe: (1) applicable circumstances preceding the violation, (2) effects of the violation upon'-facility components,

systems, or structui es, and (3) corrective action +ken to prevent recurrence; F

c. The Safety Limit Violation Report shall be submitted; within 14 days of'he violation;" to'h'e 'Co'mmission, the Manager-Corporate Nuclear Safety Section, and the Vice President-Harris Nuclear Project; and d. Operation of the unit shall not be resumed until authorized by the Commission. 6.8 PROCEQURES ANO PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below: a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; The emergency operating procedures ~equired to implement the require-ments'f NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Generic Letter,No. 82-33. Security Plan implementation; d. Emergency Plan implementation; e. PROCESS CONTROL PROGRAM implementation; f. OFFSITE 00SE CALCULATION MANUAL implementation; SHEARON HARRIS - UNIT 1 6-16

. ADMINISTRATIVE CONTROLS PROOF ANO RBIEI COPY PROCEDURES AND PROGRAMS Continued c. Seconda Mater Chemist Continued AW/IC',If%hi JUN I86 6. A procedure identifying (a) the authority responsible for the interpretation of the data and (b) the sequence and timing of administrative events required to initiate corrective action. d. Backu Method for Determinin Subcoolin Mar in A program that will ensure the capability to monitor accurately the Reactor Coolant System subcooling margin. This program shall include the following: 1. Training of personnel, and 2. Procedures for monitoring. e. Post-Accident Sam lin A program that will ensure the capability to obtain and analyze, under accident conditions, reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples. The program shall include the following: 1.. Training of personnel, 2. Procedures for sampling and analysis, and 3. Provisions for maintenance of sampling and analysis equipment. f. Ins ections of Water Control Structures A program to implement an ongoing inspection program in accordance with Regulatory Guide 1.127 (Revision 1, March 1978) for the main and auxiliary dams, the auxiliary separating dike, the emergency service water and discharge

channels, and the auxiliary reservoir channel.

The program shall include the following: 1. The provisions of Regulatory Guide 1.127, Revision 1, to be implemented as a part of plant startup operations. 2.".".Subsequent inspections at yearly intervals for at least the next, 3 years. If adverse conditions are not revealed by these ~ ',:inspections; inspection at 5-year intervals will be performed. 3..;" The program shall specify a maximum sediment depth that will be permitted to accumulate in the channels before removal is required. Tu.g.ggalg Alvc Alwo cAIAA wheal aAc'a]go o 4I AAr Aimed t.~ ~~~+'PL +4< >444~<+ gw wee ouedc %@corn 4+8 A S. /ASZR7 $ Pga~ Ngg SHEARON HARRIS-6"19

go TURBzJZ Reit>R IWPccTlo~ A'oSR8l9 M l4s'c CegJ/ AJ AJSo/4$ /<sPz<77oAJ OF 77fg sou Aesso//z. zan/3/uc, Eomw ~, 7R /~o ezz~ saic~ f. &~o~ v&JDoR 8zc<n wN 0877'/$ 0> XoD /RauuR< Porc/ lA4Pg/ T7onJ />iYRI/8~ 848 A'0~8 ~88 / Bl/ldz2 l&EJ~ JF'R//egj>6 /O'dA$, Azea~cuMig MK /A6'ldc77>N J>~vh'g I/~do< &~77/ODOc Od/ SHNPP g)~/ }Q ) CE 4 I JUN 1986

SHg pp ELECTRICAL POWER SYSTEMS R +StON JOIE gag BASES P800F ANO EEIEN ESPY A. C. SOURCES 0.C. SOURCES AMD..ONSITE POWER DISTRIBUTION Continued The OPERABILITY of the minimum specified A.C. and O.C. power sources and asso-ciated distribution systems during shutdown and refueling ensures that: (1) the facility can be maintained in the shutdown or refueling condition for extended time periods, and (2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status. The SOrvefllance Requirement for demonstrating the OPERABILITY of the station batterfes are based on the recommendations of Regulatory Guide 1;329, "Mainte-nance Testing and Replacement of Large Lead Storage. Batteries for Nuclear Power Plants," February 1978, and IEEE Std 450-1980, "IEEE Recommended Practice for Maintenance,

Testing, and Replacement af Large Lead Storage Batteries for Generating Station's and Substatfons."

Verffyfng average electrolyte temperature above the minimum for which the battery was sfzed, total battery terminal voltage on float charge, connection resistance

values, and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle higb discharge rates, and compares the battery capacity at that tfme with the ~ated capacity.

Table 4.8-2 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage, and specific gravity. -The lfmfts for the designated pilot cells float voltage and specific gravity," greater than 2.13 volts and 0.015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a low value, fs characteristic.'.of".i charged cell with adequate capacity. The normal limits for each connected,;cell for.float voltage and specific gravity, greater than 2. 13 volts and'.not",mor'; than.0. 020 below the manufacturer's full charge specific ~ gravity wfthb'an".average<<specific gravity of all the connected cells not more than 0.010'.bel'ow. the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of the battery. Operation with a battery cell's parameter outside the normal limit but within the allowable value speciffed in Table 4.8-2 is permitted for up to 7 days. During this 7-day period: (1) the allowable values for electrolyte level ensures no physical damage to the plates with an adequate electron transfer capability; (2) the allowable value for the average specific gravity of all the cells, not more than 0.020 below the manufacturer's recommended full charge specific gravity, ensures that the decrease in rating will be less than the safety B 3/4 8"2 SHEARON HARRIS - UNIT 1 The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are fn accordance with the recommendations of Regulatory Guides 1.9, "Selection of Diesel Generator Set Capacity for Standby Power Supplies," gzcma~ /gp

1.108, "Perfodfc Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977 as modiffed in accordance with the gufdance of IE Notice 85-32, April 22, 1985; and 1.137, "Fuel-011 Systems for Standby Ofesel Generators,"

Revision 1, October 1979.

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