ML18022A430

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Forwards Addl Comments on Final Draft Tech Specs,Including Justification & 14 marked-up Pages for Comments
ML18022A430
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 09/18/1986
From: Zimmerman S
CAROLINA POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NLS-86-357, NUDOCS 8609240127
Download: ML18022A430 (27)
v • d • e


Text

REGULA fY lNFORNATION DISTRIBUTI SYSTEH (R IDS)

ACCESSION NBR: 8609240127 DOC. DATE: 86/09/18 NOTARIZED: NO DOCKET FAC IL: 50-400 Sh earon Harri s Nuclear Power Plant> Uni t i. Car ol ina 05000400 AUTH. NAliE AUTHOR AFFILIATION ZINllERi~fAN>S. R. Carolina Power 8< Light Co.

RECIP. NANE RECIPIENT AFFILIATION DENTON> H. R. Office of Nuclear Reactor Regulation> Director (post 851125

SUBJECT:

Forutards addi comments on final draft Tech Specs> including justification 8< 14 marked-up pages for comments.

DISTRIBUTION CODE: B001D COPIES- RECEIVED: LTR ENCL SI ZE:

TITLE: Licensing Submittal: PSAR/FSAR Amdts 5 Related Correspondence

'NOTES:Application for permit renewal f iled. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NANE LTTR ENCL ID CODE/NAKE LTTR ENCL PWR-A EB 1 1 PWR-* EICSB 2 2 PWR-A FOB 1 1 PWR-A PD2 LA 1 PWR-A PD2 PD 1 BUCKLEY> B 01 2 2 PWR-A PSB PWR-A RSB 1 INTERNAL: ADN/LFNB 0 ELD/HDSi 0 IE FILE 1 IE/DEPER/EPB 36 1 IE/DGAVT/GAB 21 1 NRR BWR ADTS 0 NRR PWR-B ADTS 0 .L 1 NRR/DHFT/NTB 1 04 1 R(:N2 3 3 RN/DDANI/NIB 0 EXTERNAL: BNL(ANDTS ONLY) 1 DMB/DSS (ANDTS)

LPDR 03 1 NRC PDR 02 NSIC 05 1 PNL GRUEL> R TOTAL NU>]HER OF COPIES REQUIRED: LTTR 30 ENCL 25

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SICK Carolina Power 8 Light Company SERIAL: NL'S-86-357 SEP 18 $ 88 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 COMMENTS ON FINAL DRAFT TECHNICAL SPECIFICATIONS

Dear Mr. Denton:

Carolina Power R Light Company submits additional comments on the final draft Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant. Attachment 1 provides seven comments (Record Numbers 739 and 800 through 805) on the TS as well as a justification for each comment. Attachment 2 provides a marked-up copy of fourteen TS pages for the corresponding comments provided in Attachment l.

If you have any questions, please contact Mr. Gregg A. Sinders at (919) 836-8168.

Yours very truly, S.. Zim erman anager Nuclear Licensing Section SRZ/GAS/pgp (0095 GAS)

Attachments cc: Mr. B. C. Buckley (NRC)

Mr. G. F. Maxwell (NRC-SHNPP)

Dr. 3. Nelson Grace (NRC-RII)

Mr. R. A. Benedict (NRC) 8609240127 860918 PDR ADOCK 05000400 FDR 411 Fayettevilte Street o P. O. Box 1551 ~ Raleigh. N. C. 27602

ATTACHMENT 1

~ ~ t CP8cL Cummcent m RHNP'P", F'intel De-aa+C Tmc:Anic=ml Rptcec:X+ic=aa.t;xmnss Record Number: 739 Comment Type: ERROR LCO Number: 3. 08. 01. 01 Page Number: 2/4 8-7 5 8 Section Number: 4.'8. l. 1.2. f . 10 Comment:

ADD A NEW ITEM 4. 8. 1. 1. 2.f. 10.f,AS FOLLOWS:

Loss of generator potential transformer circuit.

ADD TO ITEM 4.8. 1. 1. 2.f .6.c "loss of generator potential transformer circuit" AS AN ADDITIONAL SIGNAL.

ADD TO BASES PAGE B 2/4 8-2 AT THE END OF THE SECOND PARAGRAPH THE FOLLOWING SENTENCE:

"The inclusion of the loss of generator potential transformer circuit loci:out trip is a design feature based upon coincident logic and is an anticipatory tr ip qr ior to diesel generator overspeed."

Basj s THE ADDITION QF THESE ITEMS IS NECESSARY TO ENSURE THAT ALL DIESEL LOCKOUT FEATURES ARE TESTED. THE BASES HAVE BEEN REVISED TO EXPLAIN THE REASON FOR THE INCLUS I QN OF THIS LOCKOUT IN THE SURVEILLANCE PER REQUEST FROM 3.T. BEARD OF NRR.

CPScL Camman<a BHNPP Final Drake Technical Bpeci+icatiana Record Ni<<rober: 800 Comment Type: IMPROVEMENT LCQ Number: 3.03.02 Page Number: 2/4 3-38 l4 40 Sect.ion Number: TABLE 3.3-5 Comment.:

ON PAGE 3/4 3-38 ADD NOTE "(9>" TO THE RESPONSE TIME FOR ITEMS 4b, 6, AND 7.

ON PAGE 3/4 i-40'ADD A NEW NOTE (9) AS FOLLOWS:

(9) Applicable to Main Steam Isolation Valves and Main Steam Bypass Isolation Valves only., Other valves that get an MSIV signal (e.g. MS drains to condenser) are covered in Table 3.6-1.

QN PAGE 3/4 3-40 ADD THE FOLLOWONG SENTENCE TQ NOTE (2):

Other valves that get a Feedwater Isolation signal (e.g. ammonia and hydra".ine connections> are covered in Table 3.6-1.

Basi 5 msreQ THIS CHANGE IS NECESSARY TO CLARIFY t%2~ VALVES ARE REQUIRED TO HAVE A RESPONSE TIME OF 12 SECONDS. THE CONTAINMENT ISOLATION VALVE TABLE 3 ~ 6-1 LISTS SEVERAL VALVES UNDER MAIN STEAM LINE ISOLATION WHICH HAVE CLOSURE TIMES OF (60. THESE VAt VES ARE NOT ASSUAGED IN THE ANALYSIS TQ CLOSE IN THE 12 SECONDS THAT THE BYPASS AND MAIN STEAM

'ISOLATION VALVES ARE ASSUMED TO CLOSE. THIS CHANGE WILL CLARIFY THAT ONLY THE MAIN STEAM ISOLATION AND MAIN STEAM BYPASS ISOLATION VALVES ARF REQUIRED TO CLOSE IN 12 SECONDS.

A SIMII AR WORDING CHANGE IS PROPOSED FQR NOTE (a)

OF TABLE "'.='-5 QN THE MAIN FEEDWATER SYSTEM.

CPScL Commara<%-

RHNPP F'inm3. Dr ea.+4 TceaAniaa.l &~ma%,+9.aaaCiunss.

Recor d Number: 801 Commen t. Type: ERROR LCO Number: 6.02.02 Page Number: 6-4 Section Number: FIGURE 6-2 Comment:

ON THE FIGURE FOR THE PLANT ORGAN I ZAT I QN ADD THE TITLE "PLANS AND PROGRAMS" TQ THE TABLE.

Basi s THIS CHANGE IS PURELY AN ADMINISTRATIVE CHANGE IN THAT THE TITLE OF THE POSITION QF "PLANS AND PROGRAMS" IS A NEW POSITION CREATED WITHIN THE PLANT ORGANIZATION. THE FSAR IS CURRENTLY BEING REVISED AND WILL SHOW THIS NEW POSITION.

CP8cL Commanta SHNPP Final Draft Technical Speci+icatinns Recard Number: 802 Camment TYpe ERROR LCQ Number: 3. 08. 04. 01 Page Number." 3/4 8-32, Z6,38 Sect.ian Number: TABLE ~.8-1 Comment.:

QN PAGE 3/4 8-32 CHANGE THE VALUE OF THE PRIMARY PROTECTION FOR ITEMS 176 AND 179 TQ "6 A FUSE".

QN PAGE 3/4 8-36 CHANGE THE VALUE OF THE PRIMARY PROTECTION FOR ITEM 240 TO "110 A BREAKER".

ON PAGES 3/4 8-iB AND 38a CHANGE THE EQUIPI'IENT DESCRIPTIONS FQR ITEMS 275, 276, 277, 278, 284, 285, 286, 287, AND 288 FROM "RA-ICA-.... ~ " TO "RA-1CR-..... " .

QN PAGE 3/4 8-38a CHANGE THE VALUE OF THE SECONDARY PROTECTION FOR ITEM 286 TO "15 A BREAKER".

Basl s ALL OF THE CHANGES IN THE PRIMARY AND SECONDARY PROTECTION ARE DUE TO RECENT PLANT DESIGN CHANGES.

THESE CHANGES ARE NECESSARY FOR THE TECH SPECS TO AGREE WITH THE AS-BUILT PLANT CONFIGURATION. THE CHANGES TO THE EQUIPMENT DESCRIPTIONS ARE TO CORRECT ERRORS THAT WERE MADE IN TRANSCRIBIflG THE I NFQRMAT I Qtl FROt'1 QNE DOCUMENT ONTO THE PAGES SUBMITTED TQ THE NRC REVIEWER.

CP8cL Cammant;a SHNPP Pina,1 Dr aa,+C Tmc=Anic=ax,l Spume=i.+iaaa,Ciun~

Record Number: B02 Comment; Type: IMPROVEMENT LCO Number: 3. 08. 01. 01 Page Number: 3/4 B-B b Ba Becti an Number: 4. 8. 1. 1. f . 11512 Comment.e ADD NEW ITEMS 4.8. i.i.f. 11 AND . 12 AB FOLLOWS:

11) Verifying the generator capability to reject a load of between 6200 and 6400 kW without tripping.

The generat:or voltage shall not'.:ceed 7590 volts during and following the load rejectian;

12) Verifying that wi th the diesel generatar operat.ing in a test made, connected to its bus, a simulated Safety Inject.ian signal averrides t: he test mode by: (1) returning the diesel generat.or to standby operation, and (2) automatically energi"ing the emergency loads with offsite power:

Basl s THIS CHANGE IS TO INCORPORATE TWO BURVEILLANCES INTO THE SPECIFICATIONB AS DIRECTED BY THE NRR THE NEW SURVEILLANCE REQUIREMENTS ARE 'EVIEWER.

TAKEN DIRECTLY FROM THE STANDARD REV. 5 TECH SPECS EXCEPT FOR THE SPECIFIC VALUES IN ITEM f. 11. THESE VALUES ARE PLANT SPECIFIC NUMBERS AND ARE CONSISTENT WITH VALUES IN THE BALANCE OF THIS SPECIFICAT ION.

CPScL Comme nt e MMMM"F F=i.naaI.'>a-aaWW Tec=&ni.c=aaX. Mpec=9.&i.c=~&9.one's Record Number: 804 Comment Type: II'1PROVEI'1ENT "3. 08. 04. 01 LCO Number . Page Number: ~/4 8-21 'rc i5 Section Number: TABLE Z.8-1 Comment:

PAGE ~/4 8-21 ITEMS 'P, 10 b 11 IN THE COLUMN UNDER PRIMARY PROTECTION, ADD THE FQLLQNINB TO THE BREAKER SIZE:

"with a 200 A sensor".

PAGE 3/4 8-35 ITEMS 22'P. 230 Ilc 231 IN THE COLUMN UNDER PRIMARY PROTECTION, ADD THE FQLLOLJING TO THE BREAKER SIZE:

"with a 200 A sensor ".

Basi s THIS CHANGE IS MADE TO CLARIFY THE ACTUAL PRIMARY PROTECTION OF THE EQUIPMENT AND TO ELIMINATE/

POSSIBLE CONFUSION AS TQ A PRIMARY PROTECTIVE DEVICE A HIGHER RATING THAN THE SECONDARY PROTECTION.

QA,vx'Mr'

CP8cL Cammanha SHNPP F9.nal DI-a+%. Technice1 8peci+l.cat.fane Record Number: 805 Comment. Type: IMPROVEMENT LCQ Number: 3.08 04.01 F Page Number: 3/4 8-23 ~c 36 Section Number: TABLE 3.8-1 Comment:

PAGE 3/4 8- 3 ITEMS 30, 31, 32 8c 33 AND QN PAGE 3/4 8-36 ITEMS 238, 239, 240 5 241 IN THE COLUMN UNDER PRIMARY PROTECTION, ADD Tl-lE PHRASE "at 120v A.C." TO EACH ITEM. ALSO, IN THE COLUMN UNDER SECONDARY PROTECTION FOR EACH ITEM, ADD THE PHRASE "at 480v A.C." ~

Ba51 5 THIS CHANGE IS MADE TO ELIMINATE POSSIBLE CONFUSION AS TO THE PRIMARY PROTECTION HAVING A HIGHER RATING THAN THE SECONDARY PROTECTION FOR TH I S EQUIPMENT.

ATTACHMENT 2 TABLE 3.3-5 (Continued ENGINEEREO SAFETY FEATURES RESPONSE TIMES IN1TIATING S1GNAL AND FUNCTION RESPONSE TIME IN SECONDS

3. Pressurizer Pressure--Low (Continued)
a. Safety 1njection (ECCS) (Continued)
5) 'Auxiliary Feedwater Motor-Driven < 60 Pumps
6) Emergency Service Mater Pumps < 32(1)/22(8)

?) Containment Fan Coolers < 27( )/17( )

8) Control Room Isolation N. A.
4. Main Steam Line Pressure--Low
a. Safety Injection (ECCS) 12(5)/22(4) 1} Reactor Trip < 2
2) Feedwater Isolation ('((3)
3) Containment Phase "A" Isolation < 62 /72
4) Containment Ventilation Isolation 4.75
5) Auxiliary Feedwater Motor-Driven < 60 Pumps
6) Emergency Service Mater Pumps < 32( }/22(

?} Containment Fan Coolers < 27(1)/17(8)

8) Control Room Isolation N.A.
b. Steam Line Isolation
5. Containment Pressure--High-3
a. Containment Spray < 18 5 /32.2
b. Phase "B" Isolation < 22.5 /12
6. Containment Pressure-'High-2 Steam Line Isolation
7. Negative Steam Line Pressure Rate -- High Steam Line Isolation SHEARON HARRIS " UNIT 1 3/4 3-38

TABLE 3. 3-5 Continued TABLE NOTATIONS (1) Diesel generator starting and sequence loading delays included.

(2) Diesel generator starting and sequence loading delay not included.

Qffsite power available.

(3) Applicable to Main Feedwater Isolation Valves and Main Feedwater Bypass Isolation Valves~~~. Oa~A.'arom nrzr car w F<<u~>~w ~<><<~~>

ucuac. (e.g. mro~iw ~u ~yuua~z Cc'Rlpggpggg) pf+ Qov+RED W ~88c.c 3.4 "/

(4) Diesel generator starting and sequence loading delay included. RHR pumps not included.

(5) Diesel generator starting and sequence loading delays not included.

RHR pumps not included.

(6) Isolation of Normal Containment Purge. This value is no too Pre-entry Containment not app Purge which is permitted to be operating 1'l ap >ca e only in MODES 5 or 6 as per Specification 3.6.1.7.

(7) Response time testing of radiation monitors is not required.

(8) Diesel generator starting delay not included, but sequencer loading delays are included.

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S D&xds 7n edQEasEg) gpss co~Geeo J~ THAN~ ZC-/

SHNPP REVlStog 8EP 886 SHEARON HARRIS - UNIT 1 3/4 3"40

SHNPp

~EVSSfOM ELECTRICAL POWER SYSTEMS 8EP 886 A. C. SOURCES OP ERAT ING SURVEILLANCE RE UIREHENTS (Continued 4.8.1. 1. 2 (Continued) a) Verifying de-energization of the emergency buses and load shedding from the emergency buses.

b) Verifying the diesel starts*" on the auto-start signal, energizing the emergency buses with permanently connected loads in less than or equal to 10 seconds, energizing the auto-connected shutdown loads through the load sequencer, and operating for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization of these loads, the steady-state voltage and frequency shall be maintained at 6900 t 690 volts and 60 a 1.2 Hz.

5. Verifying that on a safety injection test signal (without loss of power) the diesel generator starts*" on the auto-start signal and operates on standby for greater than or equal to 5 minutes.
6. Simulating a loss of offsite power in conjunction with a safety injection test signal, and a) . Verifying de-energization of the emergency buses and load shedding from the emergency buses.-

Verifying the diesel starts"* on the auto-start signal, energizing the emergency buses with permanently connected loads in less than or equal to 10 seconds, energizing the auto-connected emergency (accident) loads through the sequencing timers, and operating for greater than or equal to 5 minutes and maintaining the steady-state voltage and frequency at 6900 k 690 volts and 60 + 1.2 Hz.

c) Verifying that all diesel generator trips,, except engine generator differential, and emergency bus dif-

~ ~ <<+~canvp overs eed feren >a are automatically bypassed upon loss of offsite

~A'coip- power signal ~ a safety injection signal.

ie eogBJrJC7VOA MITE/

""This test shall be conducted in accordance with the manufacturer's recommen-dations regarding engine prelube and warmup procedures, and as applicable r ega rdi ng 1 oadi ng recommendati ons.

SHEARON HARRIS - UNIT 1 3/4 8-7

ELECTRICAL POWER SYSTEMS SHNPP A.C. SOURCES RFvlS (AN OPERATING SE,P $ 86 SURVEILLANCE RE UIREMENTS Continued

7. Verifying the diesel generator operates"" for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel generator shall be loaded to 6800-F000 kW""" and, during the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the diesel generator shall be loaded to an indi-cated 6200-6400 kW""". Within 5 minutes after completing this 24-hour test, perform Surveillance Requirement 4.8.1.1.2. f.6 b).

8. Verifying that the auto-connected loads to each diesel generator do not exceed the continuous rating of 6500 kW;
9. Verifying the diesel generator's capability to:

a) Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power, b) Transfer its loads to the offsite power source, and c) Proceed through its shutdown sequence.

10. Verifying that the following diesel generator lockout features prevent diesel generator operation:

a} Engine overspeed b) Generator differential c} Emergency bus differential

/>SZN F~ d) e)

Emergency Stop Operational and maintenance switch in the maintenance mode.

Pm<

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least l,ass e A~~ krmart< 7ms~p arear once per 10 years or after any modifications which

't could affect diesel generator interdependence by starting"" both diesel generators simultaneously, during shutdown, and verifying that both diesel generators accelerate to at least 450 rpm in less than or equal to 10 seconds.

\

h. At least once per 10 years by:
1) Draining each main fuel oil storage tank, removing the accumu-lated sediment,'nd cleaning the tank using a sodium hypochlorite solution or other appropriate cleaning solution, and

""This test shall be conducted in accordance with the manufacturer's recommen-dations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

"""This band is meant as guidance to avoid routine overloading of the engine.

Loads in excess of this band for special testing or momentary variations due to changing bus loads shall not invalidate the test.

8If Specification 4.8.1. 1.2f.6 b) is not satisfactorily completed, it is not necessary to repeat the preceding 24-hour test. Instead, the diesel gener-ator may be operated at 6200-6400 kW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or until operating temper-ature has stabilized.

SHEARON HARRIS " UNIT 1 3/4 8-8

ni'anoErn o7od Vari fylng the ganaratnr capahkllty tn ra5act a load shall not eau C'/oo N without tripping. The generator voltage acceed 7~0 volts during and follcnrlng the load refection;

/2) <<r1 lying that with tha dlnaai generator operating in a test ablated Safety Infection signal s e by: (1) returning the di esel generator tically energiring the to standby operation, and (2) 'autoeat a

SHNPP Rev>S>oN sEP: SS

SHNPP REVfsjON TABLE 3 8 1 SEP $ 86 CONTAINMENT PENETRATION CONDUCTOR V U N Item No. Equipment Description Primary Protection Secondary Protection HOV-2CT-Y6SA-1 (Motor} 15 A Breaker 15 A Breaker (Isolation Valve)

HOV-2CT-V6SA"1 8 A Fuse 15 A Breaker (Valve Limit Switch Control)

MOV-2CT-V7SB-1 (Hotor} 15 A Breaker 15' Breaker (Isol ation Valve)

MOV-2CT-V7SB-1 8 A Fuse 15 A Breaker (Valve Limit Switch Control)

HOV-2SI-V571SA"1 30 A Br eaker 30 A Breaker (Motor}

(Isolation Valve)

MOV-2SI-V571SA"1 8 A Fuse 15 A Breaker (Valve Limit Switch-IND 8( ANN)

MOV"2SI-V570S8-1 30 A Breaker' 30 A Breaker (Hotor)

(Isol ation Val ve)

HOY-25 I-V570SB-1 A Fuse 15 A Breaker (Valve Limit Switch-IND 4 ANN)

Containment Fan Cooler 1600 A Switch 400 A Fuse AH"37 (lA"NNS) Gear Breaker 10 Containment Fan Cooler 1600 A Switch 400 A Fuse AH-38 (1A-NNS) Gear Breaker Containment Fan Cooler 1600 A Switch 400 A Fuse AH 39 (lA-NNS} Gear Breaker

'00 12 Rod Control Drive 100 A Breaker A Breaker Mech Fan E-80 (lA-NNS) 13 Rod Control Drive 100 A Breaker 100 A Breaker Mech Fan E-81 (1A-NNS) g)T>/ Al /do A ZFA5ok .

SHEARON HARRIS - UNIT 1 3/4 8"21

8-1 Continued TABLE 3.

SHNPP CONTAINMENT PENETRATION CONOUCTOR

>~'~8) ON V U N Item No. Equipment Oescription 'Primary Protection Secondary Protection 29 Reactor Coolant Pump Relay Trips Relay Trips Upstream (1A-SN) Feeder Br eaker Breaker 30 Lighting Panel (LP-105) MA Breaker V

~90 A Breaker Lighting Panel (LP"106) ldO

~A Breaker ~ A Br eaker II C"

32 Lighting Panel (LP-101) ~ra A Breaker ~CO A Brea er Panel (LP-102) k6 late'ighting A Breaker ~40 A Breaker Pressurizer Heater 90 A Breaker 100 A Fuse Back-Up (Group A) 35 Pressuri zer Heater 90 A Breaker 100 A Fuse Back-Up (Group A) 36 .Pressurizer Heater 90 A Breaker 100 A .Fuse Back-Up (Group A) 3j Pressurizer Heater 90 A Breaker 100 A Fuse Back-Up (Group A) 38 Elevator Disc Switch 100 A Breaker 100 A Breaker 39 Power Receptacles 60 A Breaker 60 A Breaker 1"2 8 1"6 40 Power Receptacles 60 A Breaker 60 A Breaker 1-9 5 1-.13 41 Power Receptacles 60 A Breaker 60 A Breaker 1-10 8( 1"14 42 Reactor Coolant Pump 30 A Breaker 30 A Breaker 1A"SN Oil BRG Lift Pump Oisk Switch for 5-Ton 50 A Breaker 50 A Breaker Monorail Pressurizer Heater 90 A Breaker 100 A Fuse Back-Up (Group A) 45 Pressurizer Heater 90 A Breaker 100 A Fuse Back-Up (Group A)

SHEARON HARRIS - UNIT 1 3/4 8-23

SHNPP REVISION TABLE 3. 8-1 Continued SEP 586 CONTAINMENT PENETRATION CONDUCTOR OVER UR N RO Y Y Item No. Equipment Description Primary Protection Secondary Protection 168 Valve 2SP-V86SB-1 6 A Fuse 15 A Breaker 169 Valve 2SP-V81SB-1 6 A Fuse 15 A Breaker 170 Valve 2SP-V15B-1 6 A Fuse 15 A Breaker 171 Val ve 2SP-VllSB-1 6 A Fuse 15 A Breaker 172 Valve 2SP-VlllSB" 1 6 A Fuse 15 A Breaker 173 Val ve 2SP-V113SB-1 6 A Fuse 15 A Breaker 174 Val ve 2SP-V114SB" 1 6 A Fuse 15 A Breaker 175 Val ve 2SP-V115SB"1 6 A Fuse 15 A Breaker 176 Cont. Fan Cooler AH-1 8J' Fuse 20 A Breaker Damper CV"DlSB-1 Motor 177 Cont. Fan Cooler AH-1 6 A Fuse 20 A Breaker Damper CV-D1SB-1 Motor 178 Cont. Fan-Cooler AH-1 6 A Fuse 20 A Breaker Damper CY-D1SB-1 Pos. Sw.

179 Cont. Fan Cooler AH-4 cfj( A Fuse 20 A Breaker Damper CV-D7SB-1 Motor 180 Cont. Fan Cooler AH-4 6 A Fuse 20 A Breaker Damper CV-D7SB-1 Motor 181 Cont. Fan Cooler AH-4 6 A Fuse 20 A Breaker Damper CV-D7SB-1 Pos. Sw.

182 RA.".1CR-356 1B-SB 0.6 A Fuse 15 A Breaker 183 RA" 1CR-356 1D-SB 0.6 A Fuse 15 A Breaker 184 Valve 2SP-V90SB-1 8 A Fuse 15 A Breaker 185 Valve 2SP-V91SB-1 8 A Fuse 15 A Breaker 186 Valve 2SP-V85SB-1 8 A Fuse 15 A Breaker SHEARON HARRIS - UNIT 1 3/4 8-32

SHNPP REV~SiON TABLE 3 ~ 8-1 Continued sEf', 586 CONTAINMENT PENETRATION CONDUCTOR Item No. Equipment Description Primary Protection Secondary Protection 220 Integrated Head 6 A Fuse 15 A Breaker Cooling Fan E-80 (18" NSS) 221 Integrated Head 6 A Fuse 15 A Breaker Cooling Fan E-81

'18" NSS) 222 Damper CV-D10-1 6 A Fuse 15 A Breaker 223 RCP-IB-SN Space Heater 15 A Breaker 30 A Breaker 224 Integrated Head 20 A Breaker 20 A Breaker Cooling Fan E-80 (18-NNS) 225 Integrated Head 20 A Breaker 20 A Breaker Cooling Fan E-81 (18-NNS) 226 AH-37 (18-NNS) Motor 15 A Breaker 15 A Breaker Space Heater 227 AH-38 (18 'NNS) Motor 15 A Breaker 15 A Breaker Space Heater 228 AH-39 (18-NNS) Motor 15 A Breaker 15 A Breaker Space Heater 229 CFC" AH-37 (18" NNS) 1600 A Breaker 400 A Fuse 230 CFC"AH-38 (18-NNS) 1600 A Breaker 400 A Fuse 231 CFC-AH-39 (IB-NNS) 1600 A Breaker 400 A Fuse 232 CROM Fan E-80 (18"NSS) 100 A Breaker 100 A Breaker 233 CRDH Fan E-81 (18-NSS) 100 A Breaker 100 A Breaker Reactor Coolant Drain 50 A Breaker 50 A Breaker Tank Pump 18 235 Containment Building 50 A Breaker 50 A Breaker Sump Pump 18-NNS 236 Incore Instrument 15 A,Breaker 15 A Breaker Drive Assemblies

~pe 8 a700 g SHEARON HARRIS - UNIT 1 3/4 8-35 gCAfog

TABLE 3. 8-1 Continued SHNPP P,wi! .=! OI'3 CONTAINMENT PENETRATION CONOUCTOR OVE CURREN PR V SEP 586 Item No. Equipment Oescription Primary Protection Secondary Protection 237 MOY-1RC- V528SN-1 15 A Breaker 15 A Breaker (8000C) 238 Lighting Panel LP-104

/W Pf A Breaker ~70 A Breaker 239 Lighting Panel LP-107 Pf A Breaker 50 A Breaker (N/E) //o 240 Lighting Panel LP-103 A Breaker L.

~ A Breaker 241 Lighting Panel LP-123

/4 A Breaker ~ co A Brea er 242 Pressurizer Heater 90 A Breaker 100 A Fuse Back-up Group "B" 243 Pressurizer'eater 90 A Breaker 100 A Fuse Back-up Group "B" 244 Pressur izer Heater 90 A Breaker 100 A Fuse Back-up Group "B" 245 Pressurizer Heater 90 A Breaker 100 A Fuse Back-up Group "B" Power Receptacles 60 A'reaker 60 A Breaker

¹1-12, 1-16 247 Power Receptacles 60 A Breaker 60 A Breaker

¹1-3, 1-7 248 Power Receptacles 60 A Breaker 60 A Breaker

¹1-4, 1-8 RCP-1B-SN Oil Bearing 30 A Breaker 30 A Breaker Lift Pump 250 Pressurizer Heater 90 'A Breaker 100 A Fuse Back-up Group "B" 251 Pressurizer Heater 90 A Breaker 100 A Fuse Back-up Group "B" 252 Pressurizer Heater 90 A Breaker 100 A Fuse Back-up Group "8" SHEARON HARRIS " UNIT 1 3/4 8"36

~ ~

8-1 Continued TABLE 3. 8HNP P ge:\IfCt~hl

~ ~

CONTAINMENT PENETRATION CONDUCTOR OV RCURR N SEP $ 86 Item No. Equipment Description Primary Protection Secondary Protection 267 Charcoal Temp. 6 A Fuse 15 A Breaker Detection Fan S-1 (lA"NNS) 268 Airborne 90 A Breaker 90 A Breaker Radioactivity Removal Unit S-1 (1A-NNS) 269 RCP-1C-SN Oil Bearing 30 A Breaker 30 A Breaker Lift Pump 270 Containment Building 50 A Breaker 50 A Breaker Sump Pump lA"NNS 271 Airborne Radioactivity 90 A Breaker 90 A Breaker Removal Unit S-l (1B-NNS) 272 Fuel Transfer Cont. 15 A Breaker ,

'15 'A Breaker Cab (Pump Motor) 273 RCC Change Fixt 15 A Breaker 15 A Breaker (Gripper Hoist Ratio Hotor) 274 Fuel Transfer 30 A Breaker 30 A Breaker Manipu]ator Crane RA - - zs'B'/ o./ A jiisE ~ A Q~hCfR RA- W-~P O.l A ~~sr /~ A B~mR

-H -8S8/ 0.4 A fuse rS' Zi'RCW~

878 RA RA-252

~ -3$ 8V

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TABLE 3. 8-1 Continued N l P~i! Istpq CONTAINMENT PENETRATION CONOUCTOR $ KP OY RCURR N P 0 Y 586 Item No. Equipment Oescription Primary Protection Secondary Protection 26's o.4 A Fits'E /~ A 8RZAA.'ER

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SHEARON HARRIS - UNIT 1 3/4 8" 38/

SH F'~hi ELECTRICAL POWER SYSTEMS sm BASES A.C. SOURCES, D.C. SOURCES AMD ONSITE POWER DISTRIBUTION (Continued The OPERABILITY of the minimum specified A.C. and D.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.

8>SED IIPOJ The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are the recommendations of Regulatory Guides 1. 9, "Selection of Diesel Generator Set Capacity for Standby Power Supplies,"

December 1979; 1. 108, "Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977 as modified in accordance with the guidance of IE Notice 85-32, April 22, 1985; and 1.137, "Fuel-Oil Systems for Standby Diesel Generators," Revision 1, October 1979. 7IIF I/cI.IIsloIII DF'77/E ~$$ OF @FATE'HTOA Po~>>I8I. TR84$ F~RPER ~AcIII'P I4CKOiIT 7Rli'S 8 DESINAI FE87IIRE BIIS~D IIPel COIdCIDZdr IO6IC mO iS WiI ~iVrICIWTORV TRIP PRI0R 7o uQSA aptRcetbg, ovggsrggo, The Surveillance Requirement for demonstrating the OPERABILITY of the station batteries are based on the recommendations of Regulatory Guide 1.129, "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 of Large Lead Storage Batteries for Generating Stations'and Substations."

Yerifying average electrolyte temperature above the minimum for which the battery was sized, 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 high discharge rates, and compares the battery capacity at that time 'with the rated 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 limits 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, is characteristic of a 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 more than 0.020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than 0.010 below 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 specified 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 8 3/4 8-2

PLANT ORGANIZATION I 0 J ~1 PLANT l4ZLEAR I SAFETY COftSTTKE DIRECTOR ASS(STANT PLANT REGS ATORY PLANT PROGRAtIS 4 GKHKRALtIAtLkGKR COMPLIAM:E PROCHXRES SKCLRITV tIAHAGER t%HAGER SLPNYISOR KHYIRON%NTAL4 (PKRATICNS TEQ%lCAL SUPPCAT RADIATICHCONNL ENVIRONMENTAL I EHGI%8VHG CKNSTRV QPERYISOR SUPERVISOR SHFT FORBIAH PAMXTSPECIAL1ST MAINTENANCE EHYIRONSET AL 8%8tYISOR 4 C%NSTRY tKCHAMCAL SEHI(R COHTRQ.

OPERATORS SRO PRMKT SPECIALIST RADIATIONCONTROL CONTROL OPERATCAS RO RADIATIONCONTROL SUPERVISOR AUXILIARYOPERATORS LEGEND AININS IAA TIVE ORSAM ZAIICN

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LIKS OF COtSXMCATION SRO - SEHICA REACTOR OPERATCRS UCKHSE RAOWASTE CPKRATIQ4 REPORT RO - REACTOR $ %RATCRS LICBISE SUPERVISOR SLPERYISOR

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