ML18019B015
| 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 BUB JECT: Forwards addi input to Final draf t 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 l P IENT COP XEB RECIPIENT COPXEB ID CODE/NANE LTTR ENCL ID CODE/NANE LTTR ENCL PWR-A EB } 1 PWR-A EICSB 2 2 PWR-A FOB 1 PWR-A PD2 LA 1 1 PWR-A PD2 PD 1 BUCNLEY> 8 01 2 PWR-A PSB 1 PWR-A RSB } 1 INTER NAL: ADN/LFl'18 1 0 ELD/HDS} 0 XE FILE IE/DEPER/EPB 36 1 XE/DGAVT/GAB 21 1 1 NRR BWR ADTB 0 NRR PWR-8 ADTS 0 NRR RQE> N. L i 1 NRR/DHFT/HFIB 1 1 NRR/DHFT/NTB 1 04 1 RGN2 3 3 Rtt/DDANI/NIB 1 0 EXTERNAL: 24X BNL(ANDTB ONLY) 1 1 DNB/DBB (ANDTS) 1 LPDR 03 1 NRC PDR 02 1 1 NSIC 05 PNL GRUEL R 1 TOTAL NUNBER QF COPIES REGUIRED: LTTR 32 ENCL
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SNK Carotlna Power & Light Company SERIAL: NLS-86-182 JUN O6 1986 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 TECHNICAL SPECIFICATIONS
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, S.. Zim rman Man er Nuclear tcensing Section SRZ/GAS/ccj (3923GAS) Attachment Cct Mr. B. C. Buckley (NRC) Mr. 3ohn D. Runkle Mr. G. F. Maxwell (NRC-SHNPP) Dr. Richard D. Wilson Dr. 3. Nelson Grace (NRC-RII) Mr. G. O. Bright (ASLB) Mr. Travis Payne (KUDZU) Dr. 3. H. Carpenter (ASLB) Mr. Daniel F. Read (CHANGE/ELP) Mr. 3. L. Kelley (ASLB) Wake County Public Library Mr. T. S. Moore (ASLAB) Mr. Wells Eddleman 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 8 pecif ication s Record Number: 600 Comment Type: IMPROVEMENT LCO Number: 3.07.13 Page Number: 3/4 7-42 Section Number: 4.7.13.b Comment: 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 Comment Type: IMPROVEMENT LCO Number: 3.08.01.01 & .02 Page Number: 3/4 8-1 h 9 Section Number: 3.8.1.1.b282.b2 Comment: 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 Comment Type: ERROR LCO Number: 3.07.12 Page Number: 3/4 7-41 Section Number: TABLE 3.7-6 Comment: ITEM ll CHANGE ITEM TO "lA-SA, 1B-SB, CHARGING PUMP ROOMS (el 236') AND lC-SAB 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 Comment Type: IMPROVEMENT LCO Number: - 6.06.01 Page Number: 6-16" Section Number: 6.6.l.a 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 Comment Type: ERROR LCO Number: 3.06.02.02 Page Number: 3/4 6-12 Section Number: 3.6.2.2.a Comment: 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 Comment Type: IMPROVEMENT LCO Number: 6.08.04 Page, Number: 6-19 Section Number: 6.8.4.g Comment: 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 Comment Type: IMPROVEMENT LCO Number: 3. 03. 02 Page Number: 3/4 3-32 Section Number: TABLE 3. 3-4 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 Comment Type: IMPROVEMENT LCO Number: B 3/4.08 Page Number: B 3/4 8-2 Section Number: B 3/4.8 Comment: 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 Co'mment Type: IMPROVEMENT LCO Number: 3.06.03 Page Number: 3/4 6-16 Section Number: TABLE 3.6-1 Comment: 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 nt e SHNPP Proof and Review Technical Specifications Record Number: 609 Comment Type: IMPROVEMENT LCO Number: 2.02.01 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 Comment Type: IMPROVEMENT LCO Number: 3.03.02 Page Number: 3/4 3-34 L 35 Section Number: TABLE 3.3-5 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 Comment, Type: ERROR LCO Number: 3.06.02.02 Page Number: 3/4 6-12 Section Number: 4.6.2.2.d 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 eview Tech Review Te nical S yecification a Record Number: 612 Comment Type: IMPROVEMENT LCO Number: 3.03.02 Page Number: 3/4 ~-38 Section Number: TABLE 4.3-2 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 LITTLE QR NO BENIFIT TO SAFETY WOULD BE PLANT.'URTHER, 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.
TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATIQN TRIP SETPOINTS SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE TA Z ~S TRIP SETPOIRT ALLOWABLE VALUE I I. Manual Reactor Trip H.A. H.A. ,'.A. N.A. N.A.
- 2. Power Range, Neutron Flux P
- a. High Setpoint f7.5] f4.56] 0 <[109]X of RTP"" <[111.1]X of RTP"*
- b. Low Setpoint [8. 3] [4. 56] 0 <[25]X of RTP*" <[27.1]X of RTP**
- 3. Power Range, Neutron Flux, f1.6] [0. 5] 0 <[5]X of RTP*" with <[6.3]X of RTP"" with High Positive Rate a time constant a time constant
>[2] seconds >[2] seconds
- 4. Po~er Range, Neutron Flux, f1.6] f0.5] 0 <f5]X of RTP"* with <[6.3]X of RTP*" with High Negative Rate a time constant a time constant
>[2] seconds >f2] seconds
- 5. Intermediate Range, f17. 0] f8. 41] 0 <f25]X of RTP"" <[30.9]X of RTP*"
Neutron Flux
- 6. Source Range, Neutron Flux f17.0] [10. 01] 0 <[10s] cps <[1.4 x 10s] cps
- 7. Overtemperature hT f6. W] See Note 1 See Note 2
- 8. Overpower hT [4. 9] fl.48] 58vk] See Note 3 See Note 4
- 9. Pressurizer Pressure-Low [5.0] [2. 21] [1. 5] >[1960] psig >[1946] psig
- 10. Pressurizer Pressure-High [7.'5] [5. Ol] [0. 5] <[2385] psig <[2399] psig ll. Pressurizer Water Level-High f8.0] [2 18] f1.51 <[92]X of instru- <[93.8]X of instru-ment span ment span R'I
*Loop design flow = [97,600] gpm C7 **RTP = RATED THERMAL POWER
TABLE 2.2-1 Continued TABLE NOTATIONS NOTE 1: OVERTEHPERATURE AT x'S} (1+ - T'] Kg(P,- P') - T~(SI)) (~1+ 1 . x S) 1
>T ) < ST~ (Kx Kg [T (~1~ ) +
(1 ~ ~ S) (~1~ T (1 + S) Where: AT Measured AT by RTD Manifold, Instrumentation; t
~1+ x S Lead-'ag compensator on measured AT; 1 + xzS Time constants utilized in lead-lag compensator for AT, z = [83 ss s
v, = [33 s; 1
~1+ xs Lag compensator on measured AT; Time constants utilized in the lag compensator for AT, rq = [03 s;.
AT Indicated AT at RATED THERMAL POWER; Kg ~6 l.alp K2 [0.01823l F;
~1+ t S The function generated by the lead-lag compensator for Tavg 1 + xsS dynamic compensation l aD Tgp Zs Time constants xs = [43 s; utilized in the lead-lag compensator for T, t ~ = s avg'verage temperature, F; Lag compensator on measured T 1 + rsS avg'ime constant utilized in the measured T lag compensator s z<s== [03 s.
avg
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}; 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
.0
~
0: 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 lj P 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. NOTE 2' The channel 458'p I s maximum AT Svwa
-Trip Setpoint shall not exceed
~
its computed Trip Setpoint by more than ~
/.0 9 Q
TABLE 2.2-1 Continued TABLE NOTATIONS n NOTE 3: (Continued) Kg f0.00159)/ F for T > T" and Ka = 0 for T < T", As defined in Note 3., I C 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. NOTE 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than
~
b4 CI I [0ccgQ Zo QQTE,5'~< +++~K i 6R~GC- ~ '~~~~ ~ ><c',3 l~
).9
~< ~<~<Fe..
Qg ~yegg g~g +gal S l CAW pwo Fop. Sm~VMssorz6 ls 0
1 SHNPP t~ TABLE 3.3"4 Continued RE/~i< Qu~. ~- ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS
} i WAyp~+g asm SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOMANCE .TA 1 ~S TRIP SETPOINT ALLOMABLE VALUE Dse pea s P/L~~>
- 9. Loss-of-Offsite Power ggao x +go m}.A A&I
~88+
- a. 6.9 kV Emergency Bus Undervoltage Primary N.A. N.A. N.A.
volts with with [~] volts a a < fl.O] eeeesW t}me
}
I v second time del aya~aa
.delay. ct.t4 Auo IS acwlbS cszV ciao
- b. 6.9 kV Emergency Bus N.A. N.A. N.A. > &%8%] volts ] volts ~
Secondary'ndervoltage with a ~kQ with a +gal'gggm
>gg6 second time seeesa time delay (withal del ay gwi theeA Safety Safety~"'"
Injection). as'njection). 6/
}s}}tT'%
6500
> ~89 volts > ~885 volts <sH8 with a <
second time f54.0] with second a < j~~ time 6~ delay (withour delay (without Safety Safety Injection). Injection).
- 10. Engineered Safety Features Actuation System Interlocks as Pressurizer Pressure, P-11 N.A. N.A. N.A. > [2000] psig > [1986] psig uk', pe-P-l/ }r,A. <<.A, golf Prig PRguug t 2E'4 Low"Low T, PWCA P-12 N.A. N.A. N.A. >
dOOO [553]'F PS~g
> [550.6] F d.4 Trip, P-4 N.A. N.A. N.A. N.A.
avg'eactor N.A. e.d. Steam Generator Mater Level, See Item 5.b above for all Steam Generator Mater Level Trip Setpoints P-14 and Allowable Values.
TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION HININN TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE HODES ACTION
- 8. Containment Spray Switch-over to Containment Sump
- a. Automatic Actuation 1, 2, 3, 4 14 W Logic and Actuation Relays
'I
- b. RWST Low Low See Item 7.b. above for all RMST Low Low initiating functions and requirements.
Coincident With: See Item 2 above for all Containment Spray initiating functions Containment Spray and requirements.
- 9. 'oss-of-Offsite Power II CO 6.9 kV Emergency Bus"- 3/bus 2/bus 2/bus 1, 2, 3, 4 15*
Undervoltage Primary j9Z 6.9 kV Emergency Bus"" Undervoltage Secondary 3/bus 2/bus 2/bus 1, 2, 3, 4 15* g P)+Q
- 10. Engineered Safety Features Actuation System Interlocks
- a. Pressut P-ll izer Pressure,-
Z 2 2',2,3 2 J, P, 3 20 ga b Pgg~AP gg~4 /~S CTAC P Low-Low T , P-12 2 1, 2, 3 20 Trip, P-4 1, 2, 3 avg'eactor 2 22 Steam Generator Water See Item 5.b. above for all P-14 initiating functions and req'uirements. Level, P-14
SHNt gtCPI Wg( f PR00F AHO REMEN COPy JQN ls8s TABLE 3.3-5 ENGINEEREO SAFETY FEATURES RESPONSE TIMES INITIATION SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- 1. Manual Initiation
- a. Safety In)ection (ECCS) N.A.
- b. Containment Spray N.A.
- c. Phase "A" Isolation N.A.
- d. Containment Ventilation Isolation N.A.
- e. Steam Line Isolation N.A.
- f. Reactor Trip N.A.
g.
\
Start Diesel Generator N.A.
- 2. Containment Pressure-High-1
- a. Safety Infection (ECCS)')
P7)(1)/$ 12)(5) Reactor Trip < f2)
- 2) Feedwater Isolation D)"')
- 3) Containment Phase "A" Isolation g ~~.C
- 4) Containment Ventilation Isol ation
+sf
- 5) Auxiliary Feedwater Motor-Driven < j:60)
Pumps
- 6) Emergency Service Water Pumps pz]~~~/pz]4 ~<
- 7) ContainmentI Fan Coolers $ 27) /$ 17)~
'.8)","; Control ~Room Isolation N.A.
- 3. Pressui'i'ier."'ressure-'-L'ow I ~
- a. Safety 'Infection (EGGS) < (27)(1)/t 12)(5)
- 1) Reactor Trip < f2)
- 2) Feedwater Isolation < g7)(3)
Containment Phase "A" Isolation
<<~Ca/
3)
- 4) Containment Venti1ation Isolation
~(6) 4,~s SHEARON HARRIS - UNIT 1 3/4 3-34
TABLE 3.3-5 Continued 586 86TINEEREQ SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS
- 3. Pressurizer Pressure Low (Continued)
- a. Safety Injection (ECCS) (Continued)
- 5) Auxiliary Feedwater Motor-Orfven < f603 Pumps -8
- 6) Emergency Service Mater Pumps < f323 /C223+g
- 7) Containment Fan Coolers < f273( )/f173(>>
- 8) Control Room Isolation N.A.
- 4. Hain Steam Line Pressure-Low
- a. Safety Ingectfon (ECCS) < f123 /f223
- 1) Reactor Trip < f23
- 2) Feedwater Isolatfon
- 3) Containment Phase "A" Isolation '~~'j>z<"
Contafnment Ventflatfon Isolation
,<~~(6) 4)
- 5) Auxiliary Feedwater Motor Driven < f603 Pumps
- 6) Emergency Service Mater Pumps f323(~)/f223(+
- 7) Contafnment Fan Coolers f273(1)/I 173(&3
- 8) Control Room Isolation N.A.
- b. Steam Line Isolation
.,s, pg m~
Contaf nme'nt* Pressure--Hf gh-3 it.S
- a. Contaf nment Spray -
<, fka~3 /f32. 23
- b. Pha'se "8'-'solation < f22.53 /f123
- 6. Containment Pressure>>-High-2 Steam Line Isolation L7~~
- 7. Steam Line Pressure Negativ Rate High Steam Line Isolation < E73~
SHEARON HARRIS - UNIT 1 3/4 3-35
TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRNENTATIOH RVEIL URHEN TRIP ANALOG ACTUATING MODES CHANNEL DEVICE NSTER SLAVE FOR WHICH I CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIRRATIOH TEST TEST LOGIC TEST TEST TEST ~IS RE LD M
- 8. Containment Spray Switch-over to Containment Sump (Continued)
- b. RWST Level Low-Low See Item 7.b. above for RWST Level Low-Low Sur veillance Requirements.
Coincident with: See Item 2. above for Containment Spray Surveillance Requirements. Containment Spray
- 9. Loss-of-Offsite Power
- a. 6.9 kV Emergency Bus N.A. N.A. H.A. N.A. N.A. 1, 2, 3, 4 Undervoltage-Primary
- b. 6.9 kV Emergency Bus N.A. R. N.A. H.A.
Undervoltage-Secondary
- 10. Engineered Safety Features Actuation System Inter locks
- a. Pressurizer N.A. R H N.A., N.A. H.A. H.A. 1, 2, 3 br PlQSaRIZEA Pressure, jggggAIgg P-ll P<y- P )/ al,A e. A.. N.A. 4.A. z, d,3 Os. Low-l.ow T , P-12 N.A. R H N.A..'-;
N.A. N.A. N.A. 1, 2, 3 db. Reactor Trip, P-4 H.A. N.A. N;A. R N.A. H.A. H.A. 1, 2, 3 eW. Steam Generator See Item 5.b; above for P-14 Surveillance Requirements. K Water Level, P-14 ~ ~ ~
SHMQ PA00F Atm PEIgEI I;spy CONTAINMENT SYSTEMS SPRAY ADDITIVE SYSTEM
~
LIMITING CONDITION FOR OPERATION 3.6.2.2 The Spray Additive System shall be OPERABLE with: 2738
- a. A spray additive tank containing a volume of between
~i~
[~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:
- 1. Verifying the contained solution volume in the tank, and 2.. Verifying the concentration of the NaOH solution by chemical analysis.
c 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
- d. 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
SHNPP REVIStog TABLE 3.6-1 JUN I86 CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CP&L ISOLATION APPLICABLE NO. ~(EBASCO FUNCTION
- 1. PHASE A ISOLATION 1MS-25 MAIN STM LOOP A PRIMARY <60 1~ 2,'6 (MS-V122) SAMPLING PANEL 1MS-27 MAIN STM LOOP B PRIMARY <60 (MS-V124) SAMPLING PANEL 1,2,6'60 1MS-29 MAIN STM LOOP C PRIMARY 1,2,'6 ~
(MS-V126) SAMPLING PANEL
-1CS-7 .CVCS NORMAL LTDN ISOL 10 ...,:N/A,,
(CS-V511) 1CS-8 CVCS NORMAL'LTDN ISOL 10 N/A (CS-V512) 1CS-9 CVCS NORMAL LTDN ISOL 10
'N/A (CS-V513) 1CS-11 NORMAL LTDN ISOL I'VCS 10 N/A (CS-V518) 1CS-470 CVCS SEAL VZR RETURN & EXCESS 10 N/A (CS-V516) LTDN 1CS&72 CVCS SEAL WTR RETURN & EXCESS 10 N/A (CS-V517) LTDN 33 1SP-209 GAS RETURN FROM P.A.S.S. 3p i (SP-V408) SKID 82 33 1SP-208 GAS RETURN FROM P.A.S.S. SKID 82 5 (SP-V409) 37 1CC-176 CCW TO RCDT & EXCESS LTDN 10 1,6,2 (CC-V172) HEAT EXCH.
38 1CC-202 CCW FROM RCDT & EXCESS LTDN 10 1,6,2 (CC-V182) HEAT EXCH. 40 1RC>>161 REACTOR MAKEUP WTR TO PRT C60 (RC-D525) 42 1ED-121 RCDT PUMP DISCH. 10 (WL-L600)
SHNpp >tptma ~ JUN mS6 TABLE 3,6 I (Conttd) CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CPSL ISOLATION APPLICABLE NO. ~(EEASCO FUNCTION TIME SEC NOTES 42 IED-125 RCDT PUMP DISCH 10 2 (WL-D650) 74 lED-94 CTMT SUMP PUMP DISCH c60 (MD-V36) 74 IED-95 CTMT SUMP PUMP DISCH <60 (MD-V77) 76A ISI-179 ACCUMULATOR FILL FROM RWST 10 2.3 (SI-V554) 76B ISI-263 ACCUMULATOR TO RWST 10 2t3 (SI-V555) 76B ISI-264 ACCUMULATOR TO RWST 10 2t3 (SI<<V550) 77A ISI-287 N2 TO ACCUMULATORS 10 2t3 (SI-V530) 7.7B. IRC-141 PRT N2 CONNECTION 10 (RC-D528) 77B IRC-144 PRT N2 CONNECTION 10 2 (RC-D529) 77C LED-164 RCDT - H 2 SUPPLY 10 (WG-D590) 77C IED-161 RCDT - H2 SUPPLY 10 (WG-D291) ISP-948 - . ,RCS SAMPLE <60 (SP.-,'IIL) 78A ISP.-949 f RCS SAMPLE (60 2
,, (SP-V23) n 78B ISP-40 PRESSURIZER LIQ SAMPLE 460 (SP-Vll)
SHNP P P~l8'I(. M TABLE 3.6-1 (Cont'd) JUN $ 86 CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CP&L ISOLATION APPLICABLE NO. ~EBASCO FUNCTION 78B 1SP-41 PRESSURIZER LIQ SAMPLE 460 (SP-V12) 78C asp-59 PRESSURIZER STEAM SAMPLE 460 (SP-V1) 78C 1SP-60 PRESSURIZER STEAM SAMPLE 460 (SP-V2) 78D 1SP-78 ACCUMULATOR SAMPLE 4'60 (SP-V113) 78D 1SP-81 ACCUMULATOR SAMPLE <60 (SP-V114) 78D 1SP-84 ACCUMULATOR SAMPLE 460 (Sp-vaa5) 78D 1SP-85 ACCUMULATOR SAMPLE 460 (SP-V116) 80 IIA-216 INSTRUMENT AIR SUPPLY 460 N/A (IA-V192) 88 1SP-201 LIQUID SAMPLE RETURN FROM (sp-v406), pAss sKID 81 88 -1SP-200 LIQUID SAMPLE RETURN FROM (SP-V407) PASS SKID da 91 1SW-240 SERVICE WATER FROM NNS FAN COILS 460 (SW-B89) 91 1SW-242 " SERVICE WATER FROM NNS FAN COILS <60 (SW-B90), 92 1SW-231 SERVICE WATER TO NNS FAN COILS 460 (SW-B88) . 105 1FP-347 FIRE WATER SPRINKLER SUPPLY 460 (FP-Bl)
SHNPP pal/(8)+pl TABLE 3.6-1 (Conr.$ d) JUN $ 86 CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMtJM PENETRATION CPSL ISOLATION APPLICABLE NO. ~(EBASCO FUNCTION 108 lAF-155 AUX. F.W. TO S/G A 10 1,2,6 (AF-V162) (HYDRAZINE) 108 1AF-153 AUX. F.W. TO S/G A (AMMONIA) 10 '1,2,6 (AF-V163} 109 lAF-159 AUX. F.W. TO S/G B. 10 '1$ 2.6 (A'F-V164) (HYDRAZINE) 109 lAF-157 AUX. F.W. TO S/G B (AMMONIA) 10 1;2,6 (AF-V165) 110 lAP-163 AUX. P.W. TO S/G C 10 ".1;2;6* (AP-V166') (HYDRAZINE) 110 lAP-161 AUX. F.W. TO S/G C (AMMONIA 10 -;;1;"'2 $ 6: (AP-V167) 1SP-12 RAD MONITOR 6 H2 ANALYZER 460 "2 (SP-V300) 1SP-915 RAD MONITOR 6 H2 ANALYZER e60 (SP-V348) 73B 1SP-941 RAD MONITOR 6 H2 ANALYZER 4'0 (SP-V301} 73B 1SP-917 RAD MONITOR 6 H2 ANALYZER a60 .2, (SP-V349) 86A 1SP-42 'YDROGEN ANALYZER 460 2 $ 3' (SP-V308) 1SP-/fan 3 86A 1SP-919 HYDROGEN ANALYZER 460 $ (SP-V314)'SP-62 86B HYDROGEN ANALYZER +60 2$ 3 (SP-V309) 86B HYDROGEN ANALYZER 460 2$3 (SP-V315)
SHNPP Q~ltgl&kl TABLE 3.6-1 (Cont'd} JUN 586 CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CP&L ISOLATION APPLICABLE NO. ~(EBASCO FUNCTION TIME SEC NOTES
- 2. PHASE B ISOLATION 1CC-208 CCW TO RCP 10 N/A (CC-V170) 36 1CC-297 CCW FROM RCP 10 N/A (CC-V184) 1CC-299 CCW FROM RCP 10 N/A (CC>>V183) 39 'iCC-249 CCW FROM RCP THERMAL BARRIERS 10 N/A (CC-V191)
- 39. 1CC-251 CCW FROM RCP THEmL BARRIERS 10 N/A (CC<<V190)
- 3. SAFETY INJECTION'ACTUATION 1CS-238 CVCS NORMAL CHARGING 10 N/A (CS-V610) 51 1BD>>ll S/G A BLOWDOWN C60 1,2,6 (BD-Vll) 52 1BD-30 S/G B BLOWDOWN 460 1;2,6.
(BD-V15) 53 1BD-49 S/G C BLOWDOWN 4. 60 1.2,6 (BD-V19) 54 1SP-217 S/G A SAMPLE <60 1',2,6 (SP-V120) C 55 1SP-222 S/G B SAMPLE c60 1,2,6 (SP-V121) 56 1SP<<'27 S/GC SAMPLE 4 60 1,2,6 (SP-V122)
- 4. CONTAINMENT VENTILATION ISOLATION 57 CP-Bl CONTAINMENT ATMOSPHERE PURGE 3.5 (CP-Bl) MAKEUP (8" )
CP-B3 CONTAINMENT ATMOSPHERE PURGE 15 2$5 (CP-B3) MAKEUP (42" }
SHNPP PPvlc't~"'UN TABLE 3.6-1 (Cont t d) $ 86 CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CP&L ISOLATION APPLICABLE NO. ~EBASCO FUNCTION TIME SEC NOTES 57 CP-B4 CONTAINMENT ATMOSPHERE PURGE 15 2t5 (CP-B4) MAKEUP (42") CP-B2 CONTAINMENT ATMOSPHERE PURGE 3.'5 (CP-B2) & MAKEUP (8") 58 CP-B 7 CONTAINMENT ATMOSPHERE PURGE (CP-B 7) EXHAUST (42") 58 CP-B5 CONTAINMENT ATMOSPHERE PURGE 3.5 5 (CP-B5) EXHAUST (8" ) 58 CP-B8 CONTAINMENT ATMOSPHERE PURGE 15 2B5 . (CP-B8) EXHAUST (42") 58 CP-B6 CONTAINMENT ATMOSPHERE PURGE 3.5 (CP-B6) EXHAUST (8") 59 CB-Bl CONTAINMENT VACUUM RELIEF (CB-Bl)
'>4 98 CB-B2 CONTAINMENT VACUUM RELIEF (CB-B2)
- 5. CONTAINKTNT SPRAY ACTUATION 1CT-50 CONTAINMENT SPRAY N/A 3 (CT-V21) 24 1CT-88 CONTAINMENT SPRAY N/A 3 ','
(CT-V43)
~ MAIN STEAM LINE ISOLATION 3 1MS-80 MSIV (S/G A)
(MS-Vl-) 1MS-81 MSIV BYPASS 10 1,2,3,6 (MS-Fl) 1MS-231 MS DRAIN TO CONDENSER 460 1,2,6 (MS-V59) 1MS-82 MSIV (S/G B) 1,4 (MS-V2)
TABLE 3 '-1 (Cput.tg CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CP&L ISOLATION APPLICABLE NO. ~EBAS CO FUNCTION lHS-83 HSIV BYPASS 10 1~2~3~6 (MS-F2) 1MS-266 MS DRAIN TO CONDENSER c 60 1,2,6 (HS-V60) lMS-84 . MSIV (S/G C) 1,3 (MS-V3) lHS-85 MSIV BYPASS 10 1,2,3,6 (HS-F3) 1MS-301' MS DRAIN TO CONDENSER 460 1~2,6 (MS-V61)
- 7. MAIN'EEDWATER 'LINE 'SOLATION 1FW-159 FEEDWATER LOOP A 1,2,6 (FW-V26) 1FW<<307. FEEDWATER LOOP A BYPASS VALVE 10 1,2,6 (FW-V123) 1FW-165 FEEDWATER LOOP A (HYDRAZINE) (60 1,2,6 (FW-V89)
. 1FW-163 FEEDWATER LOOP A (AMMONIA) <60 1,2,6 (FW-V90) 1FW-277 FEEDWATER LOOP B 1,2,6 (FW-V27)
.1FW-'319 FEEDWATER LOOP B BYPASS VALVE 10 lj2,6 (FW-V124).
Cg 'y( L/f ~ '
'll FEEDWATER LOOP B (AMMONIA) c 60 1,2,6 1FW-279'FW-V91)',".
L. 1FW-281 FEEDWATER LOOP B (HYDRAZINE) < 60 1,2,6 (FW-V92) 1FW-217 FEEDWATER LOOP C 1,2,6 (FW-V28) 1FW-313 FEEDWATER LOOP C BYPASS VALVE 10 1,2,6 (FW-V125)
SHNPP FtP/tc'.l~>> TABLE 3.6-1 (Cont>d) JUN 886 CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CP&L ISOLATION APPLICABLE NO. ~NBA>CO FUNCTION 1FW-223 FEEDWATER LOOP C (AMMONIA) c60 1>2,6 (FW-V93) 1FW-221 FEEDWATER LOOP C (HYDRAZINE) <60 1,2,6 (PW-V94) 108 1AF-64 AUXILIARY FEEDWATER A 10 1,2,6 (AF-V156) PREHEATER BYPASS 109 IAF-102 AUXILIARYFEEDWATER B 10 1,2,6 (AP-Vl'57) PREHEATER BYPASS 110 lAF-81 AUXILIARY FEEDWATER C 10 1;2,'6 (AF-V158) PREHEATER BYPASS 8 AUXILIARY'EEDQATER 'SOLATION 108 lAP-55 AUXILIARYPEEDWATER TO S/G A 24 1,6 (AF-V1O) 108 1AF-137 AUXILIARY FEEDWATER TO S/G A 24 1,6 (AP-V116) 109 lAP-93 AUXILIARY PEEDWATER TO S/G B 1,.6 (AF-V19) 109 lAP-143 AUXILIARYPEEDWATER TO S/G B 1,6 (AF-Vl17)
.110 LQ'-74 AUXILIARY FEEDWATER TO S/G C '24 1,6 (AF-V23) 110 1AP-149.,;;:,.'*' 'AUXILIARYPEEDWATER TO S/G C 24 1,6 (AP-V1.18)
L
- 9. REMOTE MANUAL'VALVES ~
~
<~ pt 1MS-58 S/G PORV (S/G A) N/A 1,2,3,6 (MS-P18) 1MS-60 S/G PORV (S/G B) N/A 1,2,3,6 (MS-P19) 1MS-62 S/G PORV (S/G C) N/A 1,2,3,6 (MS-P20)
SHNPP . p~iipfr.>> TABLE 3.6-1 (Cput:Ed) JUN )986 CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CPSL ISOLATION APPLICABLE NO. ~(EBASCO FUNCTION NOTES 1CS-341 CVCS SEAL WATER TO RCP A N/A N/A (CS-V522) 10 1CS-382 CVCS SEAL WATER TO RCP B N/A N/A (CS-V523) 1CS-423 CVCS SEAL WATER TO'CP C N/A N/A (CS-V524) 13 1SI-340 . SI-.LOW HEAD TO COLD LEGS N/A (SI-'579) 14 1SI-341 SI-LOW HEAD TO COLD LEGS N/A, (SX-V578) 15 lRH-2 RHR PUMP SUCTION (TRAIN A) N/A 1,3 (RH-V503) 16 1RH-40 RHR PUMP SUCTION (TRAIN B) N/A 1,3 (RH-V501) 18 1SI-359 SI LOW HEAD TO HOT LEG N/A (SI-V587) 20 1SI-107 SI HIGH HEAD TO HOT LEG N/A ,.3 (SX-V500) 21 1SX-86 SI HIGH HEAD TO HOT N/A (SI-V501) LEG'I 22 1SI-52 HIGH HEAD TO COLD LEG N/A (SX-V502) 1SW>>92 SERVICE WATER TO FAN COOLER AH-3 N/A 1,6 (SW-B46)- 26 1SW-9I. SERVICE WATER TO FAN COOLER AH-2 N/A 1B6 (SW-B45) 27 'SW>>225 SERVICE WATER TO FAN COOLER AH-1 N/A 1,6 (SW-B52) 28 1SW-227 SERVICE WATER TO FAN COOLER AH-4 N/A 1,6 (SW-B51) 29 1SW-97 SERVICE WATER FROM FAN COOLER AH-3 N/A 1,6 (SW-B47) 30 1SW-109 SERVICE WATER FROM FAN COOLER AH-2 N/A 1,6 (SW-B49)
SHNPP RFVIQI~" ~ TABLE 3.6-1 (Cont'd} JUN $ 86 CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CPSL ISOLATION APPLICABLE NO. ~(EBAS CO FUNCTION 31 1SW-98 SERVICE WATER FROM FAN COOLER AH-1 N/A 1,6 (SW-B48) 32 1SW-110 SERVICE WATER FROM FAN COOLER AH-4 N/A 1,6 (SW<<B50) 1'7 1SI-3 SI TO HIGH HEAD COLD LEG N/A (SI-V505.)'SI-4 17 SI TO HIGH HEAD COLD LEG N/A (SI-V506) 2, 1MS-70 MAIN STEAM B TO AUXILIARYF.W. TURBINE N/A 1 3,6 (MS-V8) 1MS-72 MAIN STEAM C TO AUX. F.W. TURBINE N/A 1;,3,6 (MS-V9) 63 CM-B5 . H2 PURGE EXHAUST N/A (CM-B5)
- 10. 'MANUAL'ALVES 17 1SI-43 SI-HIGH HEAD TO COLD LEGS N/A 1r3 (SI-V30) 34 1LT-6 ILRT ROTOMETER (LOCKED CLOSED) N/A 2$3 (LT-V2) 41 1SA-80 SERVICE AIR (LOCKED CLOSED) N/A 2'3 (SA-V14) 42 1ED-119 .': RCDT PUMP DISCH BYPASS N/A 2$ 3 (WL-D651),
44 1SF-145-, . REFUELING CAVITY CLEANUP N/A 2>>3 (SF-D164) (LOCKED CLOSED) 44 1SF-144 REFUELING CAVITY CLEANUP N/A 2/3 (SF-D165) (LOCKED CLOSED) 1SF-118 REFUELING CAVITY CLEANUP N/A 2 ' (SF-D25) (LOCKED CLOSED) 45 1SF-119 REFUELING CAVITY CLEANUP N/A 2 3 (SF-D26) (LOCKED CLOSED)
SHNpp R~)a~g~l TABLE 3.6-1 (Cput'd) JUN )986 CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CP&L ISOLATION APPLICABLE NO. ~(EBASCO FUNCTION TIME SEC NOTES CM-B6 H2 PURGE MAKEUP (LOCKED CLOSED) N/A (CM-B6) 79 1FP-355 FIRE WATER STANDPIPE SUPPLY N/A 2B3 (FP-V44) 62 1LT-10 ILRT (LOCKED CLOSED) N/A 2B3 (LT-'V4) 63 CM-B4 H2 PURGE EXHAUST (LOCKED CLOSED) N/A . (CM-B4) 90 1DW-63 .DEMIN WATER SUPPLY (LOCKED CLOSED) N/A 2B 3 (DW>>V120) 1LT-'4 ILRT (LOCKED CLOSED) N/A 2's 3 (LT-V1) - . 108 lAF-174 WET LAY-UP TO STM GEN A AF HEADER N/A 1B2B6 (AF-V189) 109 1AF-173 WET LAY-UP TO STM GEN. B AF HEADER N/A 1,2,6 (AF-V190) 110 lAF-175 WET LAY-UP TO STM GEN. C AF HEADER N/A lp 2,6 (AF-V191) 11.. CHECK'VALVES 1CS-477 CVCS NORMAL CHARGING N'/A N/A (CS-V515) 1CS-4'71 CVCS SEAL WATER RETURN & N/A N/A
'(CS-V67). EXCESS LETDOWN 23 1CT-53' CONTAINMENT SPRAY TRAIN A N/A N/A (CT-V27) 24 1CT>>91 CONTAINMENT SPRAY TRAIN B N/A N/A (CT-V51) 35 1CC-211 CCW TO RCP N/A N/A (CC-V171) 36 lCC-298 CCW FROM RCP N/A N/A (CC-V51)
SHNPP REVELS'OM TABLE 3.6-1 (Cont'd) JUN I86 CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CP&L ISOLATION APPLICABLE NO. ~EBASCO FUNCTION 39 ZCC-250 CCW FROM RCP THERMAL BARRIER N/A N/A (CC-vso) 40 1RC-164 DEMIN WATER TO PRT N/A N/A (RC-V525) 41 1SA-82 SERVICE AIR N/A N/A (SA-V15) 59 CB-Vl CONTAINMENT VACUUM RELIEF N/A N/A (CB-Vl) 61 CM-Vl H2 PURGE MAKEUP N/A N/A (CM-Vl} 76A 1SI-182 ACCUMULATORY FILL FROM RWST N/A N/A (Sr-V15P) 77A 1SI-290 N2 TO ACCUMULATORS N/A N/A (SI-V188) 79 1FP-357 FIRE WATER STANDPIPE SUPPLY N/A N/A (FP-V48) 80 lAI-220 INSTRUMENT AIR SUPPLY N/A P/A (AI-V33) 90 1DW-65 DEMIN WATER SUPPLY N/A N/A (DW-V121) 92 1SW-233 SERVICE WATER TO NNS FAN COILS N/A N/A (SW-V142) 94A . EXCESS FLOW CHECK VALVE N/A FOR'TMT VACUUM RELIEF SENSING 94B EXCESS FLOW CHECK VALVE N/A (B)
- .."~'; FOR CTMT VACUUM RELIEF SENSING 94C EXCESS FLOW CHECK VALVE FOR N/A (B) CTMT VACUUM RELIEF SENSING 95A EXCESS FLOW CHECK VALVE FOR N/A (B) CTMT VACUUM RELIEF SENSING 95B EXCESS FLOW CHECK VALVE N/A (B) FOR CTMT VACUUM RELIEF SENSING
SHNPP pP/la)At i TABLE 3. 6-1 (Con t ') ~ gUN $ 86 CONTAINMENT ISOLATION VALVES VALVE NO. MAXIMUM PENETRATION CP6L ISOLATION APPLICABLE NO. ~BBABCO FUNCTION 98 CB-V2 VACUUM RELIEF N/A N/A (CB-V2)
'FP-V46)'ONTAINMENT 105 1FP-349 FIRE WATER SPRINKLER SUPPLY N/A N/A 12', RELIEF VALVES 1CS-.10 CVCS NORMAL LETDOWN N/A N/A (CS-R500) 15 1RH-7 RHR SUCTION PROM HOT LEG N/A (RH-R501) 16 1RH-45 RHR SUCTION FROM HOT LEG N/A (RH-R500) 1SW-95 SERVICE WATER FROM PAN COOLER AH-3 N/A (SW-Rl) 30 1SW-107 SERVICE WATER FROM FAN COOLER AH-2 N/A (SW-R3) 31 1SW-96 SERVICE WATER FROM RAN COOLER AH-1 N/A (SW-R2) 32 1SW-108 SERVICE WATER FROM PAN COOLER AH-4 N/A (SW-R4)
8HNF p RPV f8]~~i JUN gag TABLE 3.6-1 (Cont'd) (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.
saaoF Axo aaoEI goI y TABLE 3. 7-6 AREA TEMPERATURE MONITORING
~ 8r HAXIHUH TEMP fFEATURE AREA LIMIT 4F REACTOR AUXILIARYBUILDING
- 1. Control Room Envelope, (El 305') 85
- 2. Process IKC, Room (El 305') 85
- 3. Rod Control Cabfnets Area (El 305') 104
- 4. AM Battery Rooms (El 286') 85
- 5. AS Swftchgear Roams (El 286'). 90
- 6. Mafn Steam, Feedwater Pfpe Tunnel (El 286' 261') 116 SALSB Electrfcal Penetratfon Areas (El 236')
I
- 7. 104 ~
- 8. Area wfth HCC IA35HSA and IB35SB 104.
- 9. HVAC Chfllers, Auxflfary Rf Pfpfng 4 Valve Area (El 236') 104 CCW Pumps, CCW Hx, Auxflfary FW Pumps Area (El 236')
10.
- u. IA-SA, IB-'SB,+IC-SAB (El 236') AALU
~~~ Chargfng Pump Rooms 104
'04
~
lg8 ~
- 12. Servfce Water Booster Pump 1B-SB . '04
- 13. Hechanfcal and Electrfcal Penetratfon Areas (El 236') 104
- 14. Contafnment Spray Addftfve Tank, and NN Equfpment Area tEl 216')
- 15. Trafns ASS Cantafnment Spray Pump, RHR Pump, NLV Equfpment Areas 104.
FUEL HANDLING BUILDING
- 16. Trafns AS Emergency Exhaust System Areas (El 261') 104
- 17. Fuel Pool Coolfng Pump and Heat Exchanger Area (El 236') 104 WASTE PROCESSING BUILDING 1S. 66V Kqu<pnont Room] (Kl 236')
MISCELLANEOUS I9,. Condensate'Storage Tank Area (El 261') I22
- 20. Ofesel fuel Of 1 Storage Bufldfng (El 242') 122 2L ,Emi'rgency Servfce Water Electrfcal Equfpment Room 104 22:."-'Emergency 'Se&fce Water Pump Roam I22 23.: "=..IA';SA~Ci 18-SB"- Exhaust Sflencer Raoms (El 292') 122
- 24. IA-;.SA 4 IB-SB'8N Equfpment Rooms (El 292') 122
- 25. IA-SA 4 IB-SB %V Equfpment Rooms (El 280') IIO
- 26. IA-SA 4 IB-SB Electrfcal Rooms (El 261') 104
- 27. IA-SA 8 IB-SB Dfesel Generator Rooms (El 261') 120 SHEARON HARRIS - UNIT I 3(4 ?-41
SHXPP
~ REVISION JUN $ 86 PROOF A'IO ABlB t,'OPy PLANT SYSTEMS 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
SHNpp RFV~SNO~< Atl0 RB)D'k COPY 3/4.8 ELECTRICAL POWER SYSTEMS 198'ROOF QUID 3/4.8. 1 A.C. SOURCES OPERATING LIHITING CONOITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
- a. 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 [&~X indicated level, gpggArfc gt.S'.
R mafn fuel oll storage tank conte<ning a m$ nfmum of
<oo,~ 4&pQQG gallons of fuel~
- 3. A separate fuel oil transfer pump.
pg,feted IHf C4~$
~ l4+
APPLICABILITY: HOGES 1, 2, 3 and 4. ~ts gc,md/ ACTION:
- 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 successfully tested wfthfn the ~ either emergency diesel generator EOG has not been 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 c STANOBY wftfHn the next 6 hours and COLD SHUTDOWN within the fol-lowfng 30~hours. pffft 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
",than preplantned if the EDG became inoperable due to any cause other 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.
b
~Ju/md~ ~>E'L< R~@u/zr~zum Z u Rr Mz u/Jr IPPJJCJJQLj, ggrgJug +J 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
SHNPP PROOF AHO RBl g ggpy REyiStON ELECTRICAL POWER SYSTEHS JUN IS86 A.C. SOURCES 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 fuel, tank containing a minimum volume of t:2670] gallons of which fs equivalent to their>> jX indicated level, ~
- 2. A main fuel oil storage tank containing a minimum volume of
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~~%9 gallons and of fuel,
- 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~ Reguieens.erg ~o~ ~~~Cic~er Z 4f>C~~~< LW~C. gee Ouaiac DiZZZ~ oezgwd < >q u>> ~+~+ g~>><< g~~~~~ SHEARON HARRIS " UNIT 1 3/4 8-9
BBH IlGPY ADMINISTRATIVE CONTROLS I/' -'f PROOF AND REPORTABLE EVENT ACTION Continued JUN 85 a~ The Commission shall be notified and a report submitted pursuant to the requirements of Sectiona50.75ffto 10 CFR Part 50, and mo <o.73
- b. 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 impl ementation; SHEARON HARRIS - UNIT 1 6-16
PROOF ANO RBIEI COPY
. ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued AW/IC', If%hi JUN I86
- c. Seconda Mater Chemist Continued
- 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
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} ) CE JUN 1986
SHg pp P800F ANO EEIEN ESPY ELECTRICAL POWER SYSTEMS R +StON JOIE gag BASES 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 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. 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 SHEARON HARRIS - UNIT 1 B 3/4 8"2
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