Text

Forwards Addl Comments on Proof & Review Tech Specs.Analyses Currently in Progress Re Possible Change to Moderator Temp Coefficient Tech Spec & Terms of OT Delta T Equation.Request to Delete Fire Protection Tech Specs Will Also Be Submitted
	ML18019A751
Person / Time
Site:	Harris
Issue date:	03/21/1986
From:	Zimmerman S; CAROLINA POWER & LIGHT CO.
To:	Harold Denton; Office of Nuclear Reactor Regulation
References
	NLS-86-096, NLS-86-96, NUDOCS 8604010181
	Download: ML18019A751 (117)
	v • d • e

1.

REGULATORYIFORNATION DISTRIBUTION S~N (RIDE I ACCESSION NBR: 8604010181 DOC. D*TE: 86/03'/21 NOTARIZED: NO DOCKET 0 FACIL: 50-'400 Shearon Harris Nuclear Power 'PlantB Unit 11 Carolina 05000400 AUTH. NAME *UTHOR AFFILIATION ZIMMERMANBS. R. Carolina Power & Light Co.

RECIP. NAME RECIPIENT AFFILIATION DENTONB H. R. Of f ice of Nuclear Reactor Regulationi Director (post 851125

.~ 5M ~W C-<<<~3

SUBJECT:

Forwards addi comments on proof & review Tech Specs. Analyses currently in progress re possible change to moderator temp coefficient Tech Spec & terms of OT delta T equation. Request to delete fire protection Tech Specs will also be submitted.

DISTRIBUTION CODE: BOOID COPIES RECEIVED: LTR TITLE: Licensing Submittal: PSAR/FSAR Amdts &

J ENCL j SIZE:

Related Correspondence NOTES: Application for pei mit renewel filed. 05000400 RECIPIENT COPIES REC IP I ENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PWR-A ADTS 1 1 PWR-A EB 1 1 PWR-A EICSB 2 2 PWR-A FOB 1 1 PWR-* PD2 LA 1 PWR-A PD2 PD 1 1 BUCKLEY'S B 01 2 2 PWR-A PSB 1 1 PWR-A RSB 1 1 INTERNAL; *DM/LFMB 0 ELD/HDS1 1 0 IE FILE 1 1 IE/DEPER/EPB 36 1 1 IE/DGAVT/GAB 21 1 NRR BWR ADTS 1 0 NRR PWR-A ADTS 1 0 NRR'WR-B ADTS 0 NRR ROE'. L 1 1 N FT/HFIB 1 1 NRR/DHFT/MTB 1 1 1 RQN2 3 3 RM/DDAMI /MIB 1 0 EXTERNAL: 24X 1 1 BNL(AMDTS ONLY) 1 DMB/DSS (AMDTS) 1 1 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 PNL CRUELz R 1 1 TOTAL NUMBER OF COPIES REGUIRED: LTTR 34 ENCL 28

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Carolina Power & Light Company SERIAL: NLS-86-096

Ã'8 a1 )986 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 PROOF AND REVIEW TECHNICAL SPECIFICATIONS

REFERENCE:

Letter dated February 28, 1986 (NLS-86-066) from S. R. Zimmerman to Mr. Harold Denton

Dear Mr. Denton:

Carolina Power t!t: Light Company (CPRL) submits additional comments on the Proof and Review Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant (SHNPP). Attachment 1 provides comments on the TS as well as a justification for each item. Attachments 2 and 3 provide information on those discrepancies between the TS and the FSAR or SER. Attachment 0 provides a marked-up copy of the affected TS pages for each comment provided in Attachment 1.

This completes CPRL's initial review of the Proof and Review TS. However, as stated in our previous TS comment letter (Reference 1), analyses are currently in progress that may result in changes to the Moderator Temperature Coefficient TS and to the terms of the OTAT equation. CPRL will also submit a proposal to delete the fire protection TS.

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

Yours very truly, S.. Z erman Manager Nuclear Licensing Section SRZ:GAS:wc (3587GAS)

Attachments cc: Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. 3ohn D. Runkle Dr. 3. Nelson Grace (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. O. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. 3. H. Carpenter (ASLB)

Wake County Public Library Mr. 3. L. Kelley (ASLB)

Mr, R. A. Benedict (NRC) Mr. H. A. Cole 411 Fayettevilte Sttdet o P. O. Box 1551 o Raleigh, N. C. 27602 S60401018i 860321 PDR ADOCK 05000400 A PDR

P 0

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8604010181 Attachment I Comments on Proof of Reviewer TS (3447GASi'I j5 )

CP8c,L Coxnznents HNPP Proof and Review'echnical Specifications Record Number: 408 Comment Type: ERROR LCO Number: GENERAL Page Number: SEE ATTACHED Section Number: SEE ATTACHED Comment REPLACF. THE TANK LEVELS AND VOLUMES WITH THOSE ON THE ATTACHED PAGES. THE CHANGES ARE FOR PAGES 3/4 1-11, 3/4 1-12, 3/4 5-9, AND BASES 3/4 1-2.'asis THIS CHANGE IS A PARTIAL REPLACEMENT FOR THE CHANGES PROVIDED ON 2-28-86 IN RECORD NUMBER 287.

THESE CHANGES ARE NECESARY TO CORRECT ARITHMETIC ERRORS IN THE PREVIOUS CALCULATIONS. THESE VALUES ARE BASED UPON EVALUATION, FINALIZED EQUIPMENT SETPOINTS AND TANK DATA.

SEACTiVITY CQNTRGL SYSTEMS BORATEO WATER SOURCE - SHUTOOWN LIMITING CONOITION'OR OPERATION

3. 1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE:

a0 A boric acid tank with:

99oo A minimum contained borated water volume of SR@ gallons, which is equivalent to @$ 5 indicated level.

(0 Fy

2. A minimum boron concentration of [7000) ppm, and

3. A minimum solution temperature of $ 65l F.

b. The refueling water storage tank (RWST) with:

pg boa

1. A minimum contained borated water volume of L~OQ gallons, which is equivalent to Q~ indicated Co'Po ~~~

level.

~~g gg~OPP~

2. A m4a~a boron concentration of [20003 ppm, and

3. A minimum solution temperature of t:403 F.

APPLICABILITY: HOOES 5 and 6.

ACTION:

With no borated water soLtrce OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE RE UIREMENTS 4.1.2.5 The above required borated water source shall be demonstrated OPERABLE:

aO At least once per 7 days by:

1. Verifying the boron concentration of the water,

)

2. Verifying the contained borated water volume, and

3. Verifying the boric acid tank solution temperature the source of borated water.

when it is

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when it is the source of borated water and the outside air temperature is less than [40]'F.

SHEARON HARRIS " UNIT 1 3/4 I-0

REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES " OPERATING LIMITING CONOITION FOR OPERATION

3. 1.2.6 As a minimum, the following borated water source(s) shall be OPERABLE as required by Specification 3. 1.2.2:

a. A boric acid tank with:

~ /goo

1. A minimum contained borated water volume of 48%8 gallons, which is equivalent to ASN indicated level.

'f0'lo

2. A minimum boron concentration of t:7000] ppm, and

3. A minimum solution temperature of [65] F.

b. The refueling water storage tank (RWST) with:

g3(ooO

1. A minimum contained borated water volume of L~388f}] gallons, which is equivalent to QH+f indicated level.

f2'Fo bef~~ pu J 2goa pp~

2. A ~ieeaee boron concentration of t;2000] ppM

3. A minimum solution temperature of [40]4F, and

4. A maximum solution temperature of t:125]'F.

APPLICABILITY: MOOES 1, 2, 3, and 4.

ACTION:

aO With the boric acid tank inoperable and being used as one of the above required borated water sources, restore the boric acid tank to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGIN equivalent to at least 2000 pcm. at 2004F; restore the boric acid tank to OPERABLE status within the next 7 days or be in COLO SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With the RWST inoperable,,restore the tank to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SHEARON HARRIS - UNIT 1 3/4 1-12

PPillllh hr/0 Et~ilD'/ PQP7 EMERGENCY CORE COOLING SYSTEMS 3/4. 5. 4 REFUELING WATER STORAGE TANK LIMITING CONOITION.FOR OPERATION 3.5.4 The refueling water storage tank (RWST) shall be OPERABLE with:

yg,ooo

a. A minimum contained borated water volume of QhQOOOj gallons, which b.

is equivalent to ONE indicated level.

A 92.'Pe boron concentration NCAA of i20003 ppm

~of~~,k4 ~

c. A minimum solution temperature of r:403'F, and

d. A maximum solution temperature of [125)4F.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With the RWST inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within 6 hours and in COLO SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.5.4 The RWST shall be demonstrated OPERABLE:

a. At least once per 7 days. by:

l. - Verifying the contained borated water volume in the tank, and Z. Verifying the boron concentration of the water.

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when the outside air temperature fs less than 40'F or greater than 5125] F.

SHEARON HARRIS - UNIT 1 3/4 5-9

PILAF hPO 3P~)B/ LOP'f REACTIVITY CONTROL SYSTEMS DEBASES MOOERATOR TEMPERATURE. COEFFICIENT Continued within its I imits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.

3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 5551]4F. This limitation is required to ensure: (1) the moderator temperature coefficient is within it analyzed temperature range, (2) the trip instrumentation is within its normal operating range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (4) the reactor vessel is above its minimum RTNOT temperature;-

3/4.1. 2 BQRATION SYSTEMS The Boron Injection System ensures that negative reactivity control is available during each mode of faci)ity operation. The components required to perform this function include: (1) borated water sources, (2) charging/safety injection pumps, (3) separate flow paths, (4) boric acid transfer pumps, and (5) an emergency power supply from OPERABLE diesel generators.

0 With the RCS average temperature above 200 F, a minimum of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable. The boration capa-bility of either flow path is sufficient to provide a SHUTOOMN MARGIN from expected operating conditions of 1770 pcm after xenon decay and cooldown to 200 F. The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and require 46888 gallons of f70003 ppm borated water be maintained in the boric acid storage tanks or [M~g lons of 2000 ppm borated water be maintained in the refueling water storage'3g ops gal-tank (EST). l 48'oo Nth the RCS temperature below 2004F, o'e boron injection flow path is accept" able without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single boron injection flow path becomes inoperable.

The limitation for a maximum of one charging/safety injection pump (CSIP) to be OPERABLE and the Surveillance Requirement to verify all CSIPs except 'the required OPERABLE pump to be inoperable below t:335 Fg provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

capability required below 200 F is sufficient to provide a SHUTDOWN The boron MARGIN of condition requires either ~

1000 pcm after xenon decay and cooldown from 2000F to 140'F. This gallons of L7000$ ppm borated water be maintained in the boric acid storage/tanks or $ 88pkk8g gallons of 2000 ppm borated wate~ be maintained in 'the RMST. t Pg,~y SHEARN HARRIS - NIT 1 B 3/4 1-2

CP RZ Comxnenta HNPP Proof and Review Technical Specification.s Record Number: 413 Comment Type: IMPROVEMENT LCO Number: 3. Ol. 02. 0 l Page Number: 3,'4 1 -7 8 9 Section Number: FOOTNOTE Comment:

REVISF, FOOTNOE 4 BY ADDED THE FOLLOHING WORDING TO THE END:

and the reactor vessel head is in place.

Basis THIS CHANGE CLARIFIES THAT THE CONCERN FOR ONLY ONE PUMP OPERABLE NO LONGER APPLIES IF THE HEAD HAS BEEN REMOVED, SINCE OVERPRESSURIZATION CANNOT OCCUR IN THAT CONDITION. THIS CHANGE COULD FACILITATE TESTING DURING REFUELING OUTAGES.

C P KI Co mxnent a HNPP Px ooZ ance Review Tec h nical Sp ecif ications Recor d Number: 412 (:nmment Type: IMPROVEMENT LCO Vumber: 3. 01. 02. 03 Page Number: 3i4 I-9 Sect ion Number: APPLICABILITY Comment:

ADD THE "0" FOOTNOTE TO MODES 5 AND 6 Basis THIS CHANGE IS CONSISTENT WITH THE IDENTICAL CHANGE PROPOSED ON 2-28-86 IN RECORD NUMBER 2 FOR LCO 3,1.2.3. THE RESTRICTION ALSO VEEDS TO APPLY IN MODES 5 AND 6.

CPRL Commenta HNpp proof and Review Technical Specifications Record Number: 414 Comment Type: IMPROVEMENT LCO Number: 3. 01. 02. 03 Page Vumber: 2/ k 1--9

.Section Number: NEW FOOTNOTE Comment:

ADD THE FOOTNOTE MARKER "0" TO MODES 5 AND 6 IN THE APPLICABILITY SECTION.

ADD A NEW FOOTNOTE TO THE BOTTOM OF THE PAGE AS FOLLOWS:

There may be no charging/safety injection pumps OPERABLE for a period of no more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months while swapping in-service pumps. No CORE ALTERATIONS or positive reactivity changes are permitted during this time.

Basis SWAPPING FROM ONE OPFRATIONAL PUMP TO ANOTHER WILL BE ROUTINELY NECESSARY IN ORDER TO ACCOMPLISH REQUIRED fSI TESTING AND TO PERMIT MAINTENANCE ON THE PUMPS. THIS CHANGE SIMPLY PROVIDES FOR RELIEF FROM THE ADMINISTRATIVE BURDEN OF DECLARING THE LCO TO BE VIOLATED DURING THE CHANGEOVER. THE REQUIREMENTS OF THE ACTION STATEMENT ARE MAIVTAINED.

0 CPRL Comxnenta HNPP Proof and'eview Technical Specifications Record Number: 410 Commen t Type: IMPROVEMENT LCO Number: 3. 02. 03 Page Number: 3/4 Z-10 Section Number: 4.3.2.2 E.3 Comment:

4.2.3.2 DELETE "The indicated RCS total flow rate determined by process computer readings or digital voltmeter measurement and" 4.2.3.3 DELETE "when the most recently obtained v'alue of FWWn delta h, obtained per Specification 4.2.3.2, is assumed to exist.

Basis THESE CHANGES REFLECT THE FACT THAT THE SHNPP SPECIFICATION DOES NOT USE A GRAPH TO INTERRELATE FOEHN DELTA H AND RCS FLOW. THEREFORE THE VALU/E DO NOT HAVE TO BE DETERMINED TOGETHER TO OBTAIN THE APPROPRIATE RESULTS.

CP &.I Comrnenta HNPP Proof and Review Technical S pecifications Record Number: 407 Comment Type: ERROR LCO Number: 3.03.01 Page Number: 3!4 3-3 & 4 Section Number: TABLE 3.3-1 Comment:

ITEMS 15 AND 16 CHANGE THE TOTAL NUMBER OF CHANGES TO "2/PUMP", CHANGE THE NUMBER OF CHANNELS TO TRIP TO "2/TRAIN", AND CHANGE THE MINIMUM CHANNELS OPERABLE TO "2/TRAIN". THESE CHANGES ARE THE SAME FOR BOTH ITEM 15 AND ITEM 16.

Basis THIS CHANGE IS A REPLACEMENT FOR PREVIOUS RECORD NUMBER 130, WHICH IS WITHDRAWN. THE INTENT OF THIS CHANGE IS TO CLARIFY THE ACTUAL PLANT SITUATION WHICH IS TWO RELAYS PER PUMP, ONE FOR*

EACH TRAIN. TWO OUT OF THREF. ON EITHER TRAIN WILL RESULT IN A TRIP. OUR PREVIOUS SUBMITTAL OiN 2-28-86 WAS MISLEADING WITH REGARD TO THE TOTAL NUMBER OF CHANNELS.

CPS,L Cornmenta "HNPP proof and Review Technical Specification=.

Record Number'. '"'422 Comment Type: IMPROVEMENT LCO Number: 3.03.02 Page Number: 3/4 3-20 Section Number: TABLE 3.3-3 Comment:

ITEM 3:c.4 CHANGE THE NOTE TO THE FOLLOWING:

"See Table 3.3-6, Item l.a for Containment Ventilation Isolation Signal Area Monitors initiating functions and requirements."

Basis THIS CHANGE IS MADE TO BE IN AGR RENT WITH THE ACTUAL REFERENCE NEEDED AND TO BE CONSISTENT WITH THE CORRECT PLANT NOMENCLATURE AS REVISED IN RECORD NUMBER 182 OF OUR 2-28-86 SUBMITTAL,.

CPRL Cornmenta HNPP Proof and Review'echnical Specifications Record Vumber: 406 Comment Type: ERROR LCO Number: 3,03.02 Page Number: 3/4 3-31 Section Number: TABLE 3.3-4 Comment:

CHANGE THE VALUE "38.5" TO ""3.4" AND CHANGE THE VALUE "37.4" TO "20.4",

Basis THIS CHANGE IS PROPOSED TO INCORPORATE THE CORRECT TANK PERCENT INDICATIOiVS IN'CCORDANCE WITH THE FINALIZED SETPOINT DATA.

CPUT Cornme nta HNPP Proof and Review Technical S pecif ica tio r~ s Record Number'." -415 Comment Type: D1PROVEMEVT LCO Number: ',J. 03. 02 Page Vumber: 3/4 3- 32 Sect ion Number: TABLE 3. 3-4 Comment:

REVISF. ITEMS 9.a 8 b FOR THE LOSS OF OFFSITE POWFR PER THE ATTACHED MARKUP.

Basis THESE CHAiVGES ARE MADE TO INCORPORATE THE LATEST INFORMATION AVAILABLE TO US FROM OUR AUXILIARY SYSTEM STUDY. THE SPECIALIZED FORMAT IS NECESSARY BECAUSE THERE ARE REQUIREMENTS PLACED ON BOTH THE DROP01JT AND PICKUP FEATURE OF SOME OF THE RELAYS.

SAFETY CONSIDERATIONS ALSO DICTATE THE NECESSITY FOR A HIGH AS WELL AS LOW ALLOWABLE VALUE FOR 9.a AND THE SPECIFICATION OF SPECIFIC TIME DELAY INTERVALS. THF, CORRECTION OF THE "WITH" AND "WITHOUT" SAFETY INJECTION NOMENCLATURE MERELY CORRECTS A PREVIOUS ADMINISTRATIVE ERROR.

TABLE 3.3-4 Continued EHGIHEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUHENTATIOH TRIP SETPOINTS SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLONANCE TA Z ~SI TRIP SETPDINT "

ALLOWABLE VALUE

~DRo a t Pack

9. Loss-of-Offsite Power

~ yqgOe%<yolt5 haad VPn

a. 6.9 kV Emergency Bus H.A. H.A. H.A. > [48ee] vol ts Undervoltage Primary volts with with a ~Q a < [1.0] seeemt time second time del ay%~~'"

.delay. O. IS baal IXSCcarh 44 x'9 49oo

b. 6.9 kV Emergency N.A. H.A. N.A. > Dd88] volts > [88&&] volts 46 'f'/8 Secondary Bus.'ndervoltage with a WQR] with a ~g8%$ ]

second time>'+'" second time delay (withmd. delay wi the%

Safety Safety e s ~

Injection). Injection) 4 /2$

[6480/ volts [CS&] volts

'ith second a < [54.0]

time with a <

second time@0

[~]

delay (withe~+ delay (withers Safety Safety Injection). Injection).

10. Engineered Safety Features Actuation System Interlocks

a. Pressurizer Pressure, P-ll H.A. H.A. H.A. > [2000] psig > [1986] psig

b. Low-Low T, P-12 H.A.. H.A. H.A. > [553]'F > [550.6] F C. Trip, avg'eactor P-4 H.A. H.A. H.A. H.A., H.A.

d. Steam Generator Mater Level, See Item 5.b above for all Steam Generator Water Level Trip Setpoints P-14 and Allowable Values.

C.

C:

CPRX Comments HNPP Proof and Review. Techaica1 Specifications Record Number: "427 Comment Type: IMPROVEMENT LCO Number: 3.03.02 Page iVumber: 3/4 3-35 Section Number: TABLE 3.3-5 Comment:

ITEi4l 7 CHANGE THE TITLE TO "iVEGATIVE STEAM LINE PRESSURE RATE--HIGH" Basis THIS CHANGE IS PROPOSED FOR CONSISTENCY WITH THE WORDING USED ELSEWHERE IN THE TECH SPECS.

CPS'.L Coromenta "HNPP Pr oof and Review'ec hnical S pecif icatio ns Record Number':" "428 Comment Type: ERROR LCO Number: 3.03.02 Page Number: 3/4 3-38 Section Number: TABLE 3.3-5 Comment:

ITEM 11 - CHANGE "ALL AUXIKLIARY FEEDHATER PUMPS" TO "MOTOR-DRIVEN AUXILIARY FEEDWATER, PUMPS".

Basis THIS CHANGE REFLECT THE ACTUAL LOGIC USED IN THE PLANT DESIGN FOR THIS ITEM.

CP8c.I'oxnznenta "HNPP Px-oof and Review. Technical Specifications

' 1 Record Number: "423 Comment Type: IMPROVEMENT LCO Number: 3.03.02 Page Number: 3/4 3-40 Section Number: TABLE 4.3-2 Comment:

ITEM 3.c.4 CHANGE THE NOTE TO THE FOLLOWING:

See Table 4.3-3, Item l.a, for Containment Ventilation Isolation Signal Area Monitor Surveillance Requirements.

Basis THIS CHANGF. IS MADE TO BE IN AGREEMFNT WITH THE ACTUAL REFERENCE NEEDED AND TO BE CONSISTENT WITH THE CORRECT PLANT NOMENCLATURE AS REVISED IN OUR RECORD NUMBER 182 OF OUR 2-28-86 SUBMITTAL.

CP8iI Cornrnents HNPP Px.oof and Review Technical Specifications Record Number: 426 Comment Type: IMPROVEMENT LCO Number: 3.03.03.04 Page F

Number: 3/4 3-54 Section Number: TABLE 3.3-8 Comment:

CHANGE THE WORD "TO" TO THE WORD "AND".

Basis THIS CHANGE IS PROPOSED TO: CLARIFY THAT THE INSTRUMENTATION IS LOCATED. ONLY AT THE ELEVATIONS SPECIFIED AND IS NOT SPREAD BETWEEN THE ELEVATIONS.

a.ncaa CPRL Commenta HNP'Fr ooi Re~ie~ Te c h. nica.l Specif xcationg Re<. ord Number: 409 Comment Type: IMPROVEMENT LCO Number: 3,03. 03. 08 Page Number: 3/4 3-65 Section Number: 4. 3. 3. 8. 1 Comment:

INSERT A "4" IV THE SURVEILLANCE AFTER THE WORDS "TRIP ACTUATING DEVICE OPERATIONAL TEST" BOTH TIMES IT APPEARS IN 4.3.3.8.1.

ADD THE FOLLOWING NEW FOOTNOTE TO THE PAGE BOTTOM:

Setpoints for Heat and-Flame detectors need not be verified. Setpoints for Smoke detectors shall be verified on every other test interval.

Basis THIS CHANGE IS NEEDED TO MAKE THIS TESTING CONSISTENT WITH PRACTICAL AND EQUIPMENT LIMITATIONS INHERENT IN THE DEVICES AND TO BE CONSISTENT WITH GOOD ALARA PRACTICES'HERE IS NO PRACTICAL METHOD TO FIFLD TEST HEAT DETECTORS TO DETERMINE THE EXACT TEMPERATURE AT WHICH THEY WILL ALARM. AS CURRENTLY WRITTEN, THIS SPECIFICATION WOULD REQUIRE REPLACEMENT OF ALL DETECTORS ON A SIX MONTH INTERVAL TO PERMIT LABORATORY TESTING.

SIMILARLY1 THE FLAME DETECTORS HAVE A BUILT-IN TEST CIRCUIT BUT DETERMINATION OF THE EXACT INTENSITY OF ULTRAVIOLET LIGHT NEEDED TO ALARM IS A VERY SOPHISTICATED LABORATORY PROCESS, NOT A FIELD TEST. MANUFACTURER'S RECOMMENDATIONS AND VFPA CODES CALL FOR SETPOINT VERIFICATION ON IONIZATION DETECTORS ONLY DURING EVERY OTHER FUNCTIONAL TEST EVEN fÃ VERY DUSTY ENVIRONMFNTS.

THE NET RESULT OF LITERAL COMPLIANCE WITH THE SPECIFICATION AS WRITTEN WOULD BE REPLACEMENT OF ALL DETECTORS AN A SIX MONTH INTERVAL. THIS CONSTANT REPLACEMENT WOULD NOT BE IN THE BEST INTEREST OF OVERALL SYSTEM RELIABILITY AND CARR,IES WITH IT AN UNNECESSARY RADIATION EXPOSURE BURDEN DUE TO LARGER CREWS $ ND MUCH LARGER THAN NEEDED WORK SCOPE.

OUR PROPOSED CHANGE IS CONSISTENT WITH THE NFPA CODE REQUIREMENTS AND WITH THE TESTING CURRENTLY REQUIRED OF MOST ALL NUCLEAR PLANTS UNDER THE OLDER DEFINITION OF FUNCTIONAL TEST. WE SEE NO IMPROVEMENT IN SAFETY AiwlD CONSIDERABLE NEGATIVE IMPACT ON RELIABILITY AND ALARA IN THE CURRENT SPECIFICATION.

CPRL Cornxnenta, "HNPP Proof and Review'echnical Specifications Record Number: '417 Comment Type: IMPROVEMENT LCO Number: 3.03.03.08 Page Number: 3/4 3-67,68 46~3 Section Number: TABLE 3.3-11 Comment:

CHANGE TABLE 3.3-11 PER THE ATTACHED MARKUP.

Basis THIS CHANGE'IS MADE TO CORRESPOND WITH THE LATEST INFORMATION AVAILABLE TO USE FROM THE A/ED

P899I: 1lI)')0 PiP~IB'I Il0P'(

TABLE 3. 3-11 ConAKRd FIRE OETECTION INSTRUMENTATION TOTAL NUMBER QF INSTRUMENTS ELEVATION HEAT FLAME SMOKE ZONE INSTRUMENT LOCATION ~FT ~A/8 " ~A/8 * ~ll/B *

2. 0 Reactor Auxi I i a Bui 1 din Continued g4 1-A-4-CHLR HVAC Chiller Equipment Area 261. 0 0/42 .42/0 8 Cable Trays Cohf-B

,1-A-4"gLlNf Boric Acid Equipment Area 261. 0 0/12 13/0 4 Corridor Cable Trays cot-d'"A-4/ME Corridor Cable Trays 261. 0 0/g 7 12/0 COP-S 1" A-4-CQC Corridor Cable Trays 261. 0 0/4 ~ 7/0 1-A-4-CHFA Charcoal Filter Room 1A 261. 0 0/5 1O/O 1-A-4-CHFB Charcoal Filter Room 1B 261. 0 o/e 8/O 1-A-EPA Electrical Penetration. Area SA 261.0 O/15 15/0 1-A-EPB Electrical Penetration Area SB 261. 0 0/15 15/0 j-Z-s -Pv8 s~imroa/ Roo> 0 A4-/8 peer KHAN.O 8/o 1-A-5-HVA

/ g Pe /Vugg 1-A-5-HVB.

(-A-S-'N3 HVAC Room 1A S~imraaeg HVAC Room 1B

~ 8 ~~ ~> >~<

286. 0 ABC. 0 286. 0 14lo lib 15/0

@weep( fiprAv $-98 f 884.d J/O 18/0 S-d8'ucT'witchgear 1-A-ANGRA Room A 286. 0 1"A-SMGRB Switchgear Room 8 286. 0 ~ 17/0 1"A-BATA Battery Room IA 286. 0 2/o 1-A-BATB Battery Room 18 286. 0 2/0 27 27 1-A-CSRA Cable Spreading Room A 286. 0 0/gi g/0 1-g-CSRB Cable Spreading Room 8 286. 0 0/15 15/0 1-A-ACP Auxiliary Control Panel 286. 0 zlo t"A -CSFA PIC Room A ZB,o 2/O 12-A-6"RT1 Terminal Cabinet Room 305. 0 14/0 12"A-6-RCC1 Rod Control Cabinets Room 305. 0 jpd pContr 12-A-6-CRl" ol Room ACED 305. 0 +/9 12-A-6-APR1 Auxi I iary Relay Panels

~ ~

305. 0 6/0 I 2.-A-&-CRl Co~vyg)g ggw PAoea.s 305.0 q/c.

)g-if gv plH5 tfbmwpoA SHEARON HARRIS - UNIT 1

~f 8~-4 3/4 3"67 3'. 0

PROOF A",Q,Z~,'E',V I,'OPy Table 3. 3-11 Continued)

Fca TOTAL NUMBER OF INSTRUMENTS

'LEVATION HEAT FLAME SMOKE ZONE INSTRUMENT LOCATION ~FT ~A/B " ~A/B)*. (A/B)"

2. 0 Reactor Auxi 1 i a 8ui1din Continued

.y 12-A-6-PICRl Process Racks Instruments 8 Control 305. 0 8/0 Hh

>~~ I?-1-4-h'V0 crook Aoee pzhc Asrl ~cr Zcf:0 IZ-A-6-HV7 HVAC Equipment Room 305. 0 0/4'8 zy'g/0 p g.g gyp ZCEc78lcgL. ~uiANEvr PAO~c)(eM a/o z/o

-F-2-FPC Fuel Pool Cooling Pumps 8 236.0 O/16 Heat Exchangers 5-F-3-CHFA Emergency Exhaust Charcoal . 261.0 o/s S/0 perer 1 Filter A Pgy~ Pfj(P j/M'5 5-F-3-CHFB Emergency Exhaust Charcoal 261. 0 0/S s/o Filter B 5 3 I> NK Wa&

4.0 Diesel Generator 8uildin

~ALII 5-F-3-CHF-BAL Emergency Exhaust Balance 261. 0 Z(y(e 0 4

1-0-1-OGA-RM Diesel Generator 1A 261. 0 O/10 g/0 1.-0-1-OGB-RM Diesel Generator 1B 261. 0 0/10 4'/0 I

1-0-1-OGA-ASU Diesel Generator Air Starting 261.0 2/0 Unit 1A 1" 0-1" OGB-ASU Diesel Generator Air Starting 261.0 2/0 Unit 1B

1-0-1-QQA-TK Diesel Fuel Oil Oay Tank 1A 2SO. 0 a/z Mo-1-0-1-OGB-TK Diesel Fuel Oil Day Tank 1B ZSO. 0 1-0-1" QGA-ER Diesel Generator MCC 8 Control 261. 0 2/O Panel iA 1-0-1-OGB-ER Diesel Generator MCC 4 Control 261. 0 2/0 Panel 18 1-0-3-OGA"ES Diesel Exhaust Silencer 1A 292. 0 2/0

'-0-3-DGB-ES Diesel Exhaust Silencer 1B 292.0 2/0 i-D-3 PdA /l8 Atilt(<wc Avdp@'oe 8

. 4I-g peer PPV8C afz.o tjo g+g-nag-W AccmCioa &vtn+r Roon P >PC SHEARON HARRIS -%IT 1 3/4 3-68 z9z,0 <k

g- i' b'v PWrriPC SC ~Pi r Pu2Z /8'-ZZA/, AE.ZZ3'8/ 0 i~ 7-gV'Z PoRnac Z~~i'x1 S~cr gH'-Xg,~ 9/ J l 22/ 0 2 Q 7-A'V PoRndc. CuPPi Y j~r A//-Eg / gd'Q5'2P.' a)g INERT 8 iI gertnu4ie4 TV' PooH L87ZR CoflPuWQ sic, Ju~r H-P7w,~k-g7Z -- --- ')~

Co~>uWR 4QVTRY twnc7io~ /toes P-gG'ay.o

/'VS ~izeTA'IC HV8C Sue~

2/0

~~-~sw y

PROOF AHO REV!EN 00PY TABLE- 3. 3-13. Continued)

TOTAL NUMBER OF INSTRUMENTS ELEVATION HEAT FLAME ) SMOKE ZONE INSTRUMENT LOCATION ~FT '~A/8 " ~A/8)" (A/8)"

5.0 Oiesel Oi1 Stora e Tank Area 1-0-PA Diesel Fuel Oil Pump Room 1A 242. 25 0/2 2/0 1-0-PB Oiesel Fuel Oil Pump Room 18 242.25 0/2 2/0 5-0-BAL Oiesel Fuel Oil Storage Tank 242.25 7/0 ~

Area-Balance 6.0 Emer enc Service Mater Intake Structure 12-1-ESMPA E1ectrical Equipment Room SA 251. 7/ mme

$ 0/0 262. 0 Pump Room SA 262. 0 2/0 F

12-1-ESWPB Electrical Equipment Room SB 25 j. 7/ 10/0 262. 0 Pump Room SB 262.0 2/0 yA&

yi4.

SHEARON HARRIS - UNIT 1 3/4 3-69

r TABLE 5.3-11a

.r HVAC DUCT FIRE DETECTION INSTRUCTS Sup y Fan Smoke Detector Zone HVAC S stem Ta No.

1.0 Rea tor Auxilia Buildin t V 1-A-5-HUA Svitchgear Room A FAD-1FP-8655-AOl EL 286 AH-3.2 (1A-SA); (1B-SA) FAD-1FP-8655-A02 FAD-1FP&65$ '-A03 m 1-A-5-HVB itchgear Room B FAD-1FP&655-B01 EL. 286 3 (lh-SB) (lB-SB) FAD-1FP-8655-B02 FAD-1FP&655-B03 FAD-1FP-8655-B04 V 12-A-6-HV7 Electzi 1 Equipment FAD"1FP&655-COl EL. 305 Protecti Rooms FAD-1FP&655W02 HVAC AH-16 (1A-Sh)

(1B-SB) I

~2-A-7-HV NNS Ventilatio FAD-1FP-8655-D01 EL; 324 AH-14 (NNS), / FAD-1FP&655-D02 FAD-IFP"8655-D03 )

FAD-1FP"S655-D04 ~

~ 1-A-5-HV3 Normal Supply FAD-1FP&655-EOl EL. 286 S-3A (NNS) S-,3B (NNS) FAD-1FP&655-E02, FAD-1FP&655-E03

.F AD-lFP&655-E04 IFP&655-E05 y'2-AW-HV7 ControX Room HVAC F 1FP-8655-FOl EL. 305 AH-15j(1A-SA), (1B-SB) FAD- FP-8655-F02

//

FAD-1 '6&5-F03 FAD-1F -8655-F04 (Later) mputer 6 Communication FAD-1FP-8 55-601 EL. 324 R?f HVAC AH-97A(NNS) FAD-1FP-86 5W02 AH-97B(NNS)

(Later) Computer Batr cry 6 Aux FAD-1FP-8655- 1 EL. 324 Electric Protection Rms FAD-lFP&655-H HVAC AH-ogh r!".;<)

Ah~Nb (NNS) 2.0 Fuel Hnndlfn j Building

~1 AW-CHFA Normal Supply (South) FAD-1FP-8657-AOI

.L. 261 AH-21A (NNS), FAD-I F) -8057-A02 AH-2lB (hNS )

8676g

>\

0 aABL,k 3, 3-I ja HVAC DUCT FIRE DETECTION INSTRU.'L~'hTS Supply Fan Smoke Detector Zone HVAC S stem Tag, No.

/

g 5-F-3-HV L Noraal Sopp17 (North) FBDFIFP 865-7 B01-

+ EL. 261 68-226 (NNS>Q FDD2F-P&657 B0-2 AH-22B (NNS)' ~iFAD-1FP&657-B03 12-A-7-HV

+ EL. 324 Normal Supply (Ope&tFlr)

AN 56 -(NNS),

AH-57 (NNS) ~ FAD-1FP&657-C01 FAD iF-P 86-57 00-2

/ 12+-7-NV EL. 324 Normal Supply AH-58 (NNS)

Oper Fl) FAD-1FP-8657-D01 F~3.FP&657-D02 AH-59 (NN 3.0 Diesel Generator uflding

~l-D-3-DGA-HVR Zly tric Equip. FAD-1FP&658 $01 EL. 292 Rm. A HVAC AHOIS, FAD-1FP&658-M 1A-SA), AH&5 (lB-SA)

+ 1-D"3-DGB- VR Electric Equip FAD-1FP&658-B01 EL. 292 Rm B HVAC FAD-1 FP-8658-B02 AH&5 (1AWB),

AH&5 (1BWB) 86768

, l gp P6( 'I

)hliT g/g . z-(n%E

0 CPRL Cornmenta HNPP Pr oof and Review Technical Specification~

Record Number: 400 Comment 'fype: IMPROVEMENT LCO Num'be r: ."<. 03. 03. 11 Page Number: 3!4 3.-83 Section Number: TABLE 4.3-9 Comment:

ITEM 4.a CHANGE ITEM 4.a TO THE FOLLOWING:

a.l Noble Gas Activity Monitor(PIGr a.2 Noble Gas Activity Monitor(WRGM)

THE SURVEILLANCE FREQUENCIES AND MODES ARE THE SAMF. FOR BOTH 4.a.l AiVD 4.a.2.

Basis THIS CHANGF, XS MADE TO CORRECT AN ADMINISTARTIVE OVERS IGHT ~ ON 2-28-86 IN RECORD NUMBER 161, CPS'L PROPOSED TO ADD AN ADDITIONAL LINE TO THIS ENTRY IN TABLE 3,3-13. BY OVERSIGHT, WE NEGLECTED TO MARK UP THE EQUIVALEVT CHANGE IiV THE SURVEILLANCE TABLE.

NOTE THE ACRONYM .TS WRGM AND SHOULD BF. TH S WAY IN ALL LOCATIONS.

CPA J Coxnznenta HNPP Proof and Review Technical Specificationa Record Number: 403 Comment Tvpe'IMPROVEMENT LCO Number: 3.05.01 Page Number: 3,'4 5-1 Section Number: 3.5.1.b Comment:

3.5.1.b - REPLACE "7440 and 7710 gallons, which is equivalent to and indicated level between 66 and 97'evel" WITH "66 to 979'ndicated level".

3.5.1.c-- CHANGE "2100" TO "2200".

Basis THE FIRST CHANGE IS MADE IN THE INTEREST OF GREATER SIMPLICITY AND ACCURACY. THE LCO IS NOW FORMATTED THE SAME AS THAT ISSUED IN THE BYRON TECH SPECS. THE PERCENT INDICATED LEVEL IS THE OiVLY INDICATION ACTUALLY AVAILABLE SO GALLONS IS NOT A USEFUL MEASURE FOR THE TECHNICAL SPECIFICATIONS. IN ADDITION, BECAUSE OF DIFFERENT PIPING RUNS BELOW EACH ACCUMULATOR, THE ACTUAL CONTAINED VOLUME IN GALLONS IS SLIGHTLY DIFFERENT FOR EACH ACCUMULATOR AT THE SAME INDICATED PERCENT LEVEL. THE LE/ELS NOW IN THE SPECIFICATION ENSURE FOR ALL THE ACCUMULATORS THAT A MINIMUM VOLUME CONSISTENT WITH THE WORST CASE ACCIDENT ANALYSIS IS MAINTAINED AND THAT SUFFICIENT NITROGEN PRESSURIZATION IS ALSO AVAILABLE.

THE SECOND CHANGE IS PROPOSED TO BRING THE UPPER LIMIT INTO AGREEMENT WITH THE RWST LIMITS. 1900 ppm IS LEFT AS IS BECAUSE THAT IS THE LOWER LIMIT USED IN THE ANALYSIS.

CP &.L Comments HNPP Proof and Review Technical Specifications Record Number: 405 Comment Type: ERROH LCO Number: 3.05.02 Page Number: 3/4 5-4 Section Number: 4.5.2.a Comment:

IN THE COLUMN FOR CP&L VALVE VUMBERS CHANGE ALL VALVE NUMBERS FORM "ISI" TO "1SZ" Basis TYPO

CP8c.L Cornxne nta

'NPP Phoo f and Review'ec h nical S pecif icatio n s Re co rd Numb e r: '404 Commen t Type: ERROR LCO Number: 3. 05. 02 Page Number: 3/4 5-6 Section Number:

Comment:

IN THE COLUMN OF CP&L VALVE NUMBERS ALL VAIVE NUMBERS SHOULD BE CHANGED TO "1SI".

Basis THE CHANGE IS TO CORRECT A TYPO.

CP KL Coxaxaenta HNPP Proof and Review Technical Specifications Record Number: 401 Comment Type: ERROR LCO Number: 3. 06. 02. 01 Page Number: 3/4 6"11 Sect ion Number: 4. 6. 2. 1. b Comment CHANGE THE VALUE "231" TO " 45".

Basis THIS CHANGE IS TO INCORPORATE THE LATEST DESIGN AND OPERATIONAL INFORAMTION AVAILABLE TO US,

CPBr.L Cornxnents NPP Proof and Review Technical Specifications Record Number: 402 Comment Type: IMPROVEMENT LCO Number: 3.06.02.01 Page Number: 3/4 6-11 Section Number: 4.6.2.1.c Comment:

4.6.2. AC. 1 INSERT THE WORD "A" BEFORE THE WORDS "CONTAINMENT SPRAY ACTUATION" AND DELETE THE WORDS "AND CONTAINMENT SPRAY SWITCHOVER TO CONTAINMENT SUMP" ADD A NEW 4.6.2. 1.C.3 AS FOLLOWS:

Verifying that each automatic recirculation valve from the sump actuates on an RWST Lo-Lo test signal.

Basis THIS CHANGE IS MADE TO CLARIFY THE EXACT TEST SIGNAL AND TO CLARIFY THAT THE PUMP MUST BE RUNNING FOR THIS TEST TO FUNCTION PROPERLY.

CP8<.Z Coxnxnente HNPP Proof and Review Technical Specifications Be<.ord Number: 411 Comment Type: IMPROVEMENT LCO Number: .'<.06.03 Page Number: 3/ ) 6-14 Section Number: NEW FOOTNOTE Comment IN THE ACTION STATEMENT 1NSERT AN "0" AFTER THE WORDS "containment isolation valve(,s)".

ADD A NEW FOOTNOTE TO THE BOTTOM OF THE PAGE AS FOLLOWS:

Except MSIV's which are covered by Specification 3.7.1.5.

Basis THIS CHANGE IS ADDED TO CLARIFY THAT THE MSIV'S ARE GOVERNED BY THEIR OWN SPECIFICATION. DUE TO THE UNIQUE NATURE OF THE MAIN STEAM LINES, 1T CAN BE 'IMPOSS IBLE TO MEET THE STATED ACTIONS IN 3. 6. 3 SINCE THERE IS ONLY THE SINGLE MSIV.

CPRL Comrnenta HNPP Proof and Review Technical Specifications R~co vd Numb e r: 425 Comment Type: IMPROVEMEVT LCO Vumber: 3. 08. 01. 01 Page Vumber: 3/4 8-3 Section Number: 4. 8. l. l. 1. b Comment:

LINE 1 DELETE THE WORDS "DURING SHUTDOWN".

Basis THIS CHANGE IS PROPOSED TO ENABLE US TO PROPERLY DEMONSTRATE THIS FUNCTION. THIS SHOULD NOT BE DONE AT SHUTDOWN, BUT RATHER IN MODE 2 OR LOW POWER MODE 1 TO PREVENT STATION LOSS OF OFFSITE POWER.

CP8c.X Comxnenta "HNPP Proof and Review Technical Specification.s Record Number: '424 Comment Type: ERROR LCO 4umber: 3. 09. 12 Page Number: 3/4 9-14 Section Number: ACTION A Comment:

LAST WORD OF THE ACTION DELETE THE "S" FROM THE WORD "ADSORBERS".

Basis THIS CHANGE IS MADE TO MAKE THE ACTION TRUELY ACCRUATE. EACH SUBSYSTEM HAS TWO HEPA FILTERS BUT ONLY ONE CHARCOAL ADSORBER.

CPRX Cornxnenta "HNPP Proof and Review Technical Specifications Record Number: 421 Comment Type: ERROR LCO Number: 8 3/4. 06. 01. 0 "r Page Number: B Jj'L 6-2 Section Number: B 3/4. 6. l. 7 Comment:

SECOND PARAGRAPH, LINE 6 DELETE THE SENTENCE THAT BEGINS WITH "Operation with one pair...."

SECOND PARAGRAPH, LIVE 12 REWORD THE LAST THREE LINES OF THE PARAGRAPH TO THE FOLLOWING:

"...may be used to support the opening of these It isolation valves dur,.ing MODES 1, 2, 3, and Basis THIS CHANGE IS NEEDED TO BE CONSISTENT 'WITH OUR PREVIOUS PROPOSALS TO DELETE THE 1000 HOURS LIMIT ON CONTAIiVMENT PURGE. REFERENCE OUR RECORD NUMBER 193 FROM OUR 2-28-86 SUBMITTAL.

CP &X. Cornme nta HNPP Proof and Review'echnical Specifications Record Number'." "418 Comment Type: IMPROVEMENT LCO Number: 3. 12. 01 Page Number: 3/4 12-6 Section Number: TABLE 3. 12-1 Comment:

ITEM 4.b CHANGE "BLUEGILL" TO "SUNF1SH".

Basis THIS CHANGE IS PROPOSED BECAUSE IT IS FFLT THAT IT WILL PERMIT A BETTER REPRESENTATION OF SPORTFISHING PRACTICES IiV THE AREA. THE CHANGE TO SUNFISH WILL PERMIT SAMPLING OF BLUEGILL AS WELL AS MEMBERS OF THE BREAM FAMILY AND CRAPPIE FAMILY.

ALL OF THESE FISH SHARE SIMILAR FEEDING HABITS AND'LL ARE RECREATIONALLY IMPORTANT IN THE PLANT AREA.

CPRL Cornmenta HNPP Proof and Review Technical Specification~

Record Number:" 419 Comment Type: IMPROVEMENT LCO Number: R 3/4. 07. Ol. 03 Page Number: B 3/4 Section Number: B 3/4. 7. 1. 3 Comment:

ADD TO THE END OF THE PARAGRAPH THE FOLLOWING:

...,and the value has also been adjusted similar to the discussion on page B 3/4 1-3 for the RWST and BAT.

Basis THIS CHANGE IS PROPOSED TO CLARIFY THE CONSERVATIVE CHANGES FROM THE TRUE MINIMUM LEVELS.

CPRL Comxnenta "HNPP Proof and Review. Technical S pecif ica tio n. s Record Number: 420 Comment Type: IMPROVEMENT LCO iVumber: 6.02.01 8c .02 Page Vumber: 6-3 h 4 Section Number: FIG. 6.2-1 & -2 Comment:

ADD A FOOTNOTE TO THE BOTTOM OF BOTH FIGURES AS FOLLOWS:

0-The Corporate Organization may be change) without prior License Amendment~this figure provided that a 4+i I pprOpre wL g ghgugC, Cey<CS~

M~w+4s ~~ +4e e gfec4~ c colic P$ L c Q t QQAP )+ ~f L~ ~

Basis THIS CHANGE IS PROPOSED TO CLARIFY EXISTING PRACTICE IN THIS AREA AND TO BE CONSISTENT WITH WORDING &~4044RV FOR OTHER CP8 L PLANTS. ~HgS PRoP os&&

gAS CEW QOPRov6% ~y ~gC hing C. OA CTREE pLAmTS ~

CPS.L Cornnxenta

'HAPP Proof and Review Technical Specification~

Record Number: 416 Comment Type: ERROR LCO Number: 6. [0. 03 Page Number: 6-25 Sect ion Number: 6. 10. 3. i Comment:

CHANGE THE WORD "Operational" to ".Corporate".

Basis THIS WORD CHANGE WAS OMITTED FROM OUR 2-28-86 SUBMITTAL BY AN OVERSIGHT ON OUR PART'. THE CHANGE IS NEEDED TO MAKE THE REFERENCE TO THIS PROGRAM CORRECT ACCORDING TO OUR NOMENCLATURE.

~ ~

Attachment 2 Discrepancies Between FSAR and TS (3447GAS/Ijs )

CP8c.L Cornrnenta HNPP Proof and Review Technical Specifications Record Number:" 429 Comment Type: FSAR/TS DISCRFPA4('3 LCO Number: 3.0l.02.05 5 .06 Page Number: 3/4 1-l1 8 12 Section Number: 3.1.2.5 8 .6 Commen t:

THE, TECH SPECS STATE THAT THE BORON CONCENTRATION OF THE RWST SHALL BE MAINTAINED BETWEEN 2000 AND 2200 ppm. FSAR TABLE 6.2.2-9 (PAGE 6.2.2-28) AND SECTION 6.2.2.3.2.3 (PAGE 6.2.2-13) STATE THE RANGE AS 2000 TO 2400 ppm. FSAR SECTION 6.1.1.2 PROVIDES A RANGE OF 3000-4000 ppm.

THIS DESCREPENCY ALSO APPI IES TO TECH SPEC SECTION 3.5.4 Basis AN FSAR CHANGE WILL BE PREPARED 70 CORRECT THE DESCEPENCY.

CP &,L Cornxne nta "HNPP Proof, and Review. Technical Specifications Record Number:" 431 Comment Typ~: fSAR ~TS D ISCREPANCY LCO Number: 3.05.01 P'age Number: 3/4 5-l Section Number: 3.5.l.c Comment:

THE TECH SPECS STATE THAT THE BORON CONCENTRATION IN THE ACCUMULATORS SHALL BE MAINTAINED BETWEEN 1900 AND 2200 ppm. FSAR TABLE 6.3.2-1 STATES THAT THE RANGE IS 1900 TO 2100 ppm.

Basis AN FSAR CHANGE WILL BE PREPARED TO CORRECT THE DEFICIENCY.

Attachment 3 Discrepancies Between TS and SER

($ 447GAS/'s )

CPRZ Cornme nba "HNPP Proof and Review Technical S pecif ication ~,

Record Number: 430 Comment Type: SFR/TS DISCREPANCY LCO Number: .".01.02.05 8 .06 Page Number: 3/0 l. -1l 8 12 Sect ion Number: 3. 1. 2. 5 h . 6 Comment.:

SER SECTION 6.1.1 (PAGE 6-2) STATES THE BORON CONCENTRATION IN THE RWST SHALL BE GREATER THAN 2000 ppm. 'IT DOES NOT HAVE AN UPPER LIMIT ON THE RANGE AS PROV1DED IN THE TECHSPECS.

THIS DESCREPENCY ALSO APPL'IES TO TECH SPEC SECTION 3.5.4.

Basis A CHANGE TO THE SER SHOULD BE MADE.

Attachment 0 Marked-Vp TS Pages (3447GAS/Ijs )

SHWPF'g PROOF ABtj REV!BY COpY REACI.Vi..'ONTROL SYSTEMS 8%

3/4. 1. 2 BORATION SYSTEMS FLOM PATH " SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergency power source:

a. A flow path from the boric acid tank via either a boric acid transfer pump or a gravity feed connection and a charging/safety injection pump to the Reactor Coolant System fication if the boric acid tank in Speci-3.1.2.5a. or 3.1.2.6a. is OPERABLE, or .

p~~P

b. The flow path from the refueling water storage tank via a charging/

safety injection to the Reactor Coolant System if the refueling water storage tank in Specification 3.1.2.5b. or 3. 1.2.6b. is OPERABLE.

APPLICABILITY: MODES 4", 5, and 6.

ACTION:

Mith none of the above flow paths OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE RE UIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying that the temperature of the flow path between the boric acid tank and the charging/safety injec-tion pump suction header is greater than or equal to [65]'F when a flow path from the boric acid tank is used, and

b. 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.

"A maximum of one charging/safety injection pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 335 F<p~J +he Re~c+oe vessel hc pd <<<~ ~/Ioce.

SHEARON HARRIS - UNIT 1 3/4 1-7

SHNPP

/)PI~I l I'iiuOF AHO RENB/ f,'ppy REACTIVITY CONTROL SYSTEMS

.NR $ 66 CHARGING PUMP - SHUTOOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 One charging/safety injection pump in the boron injection flow path required by Specification 3. 1.2. 1 shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.

APPLICABILITY: MODES 4", 5, and 6.,

ACTION:

With no charging/safety injection pump OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILL'ANCE RE UIREMENTS

4. 1.2.3. 1 The above required charging/s'afety injection pump shall be demon-strated OPERABLE by verifying, on recirculation flow or in service supplying flow to the reactor coolant system and reactor coolant pump seals, that a differential pressure across the pump of greater than or equal to 2446 psid is

. developed when tested pursuant to Specification 4.0.5.

4.1.2.3.2 All charging/safety injection pumps, excluding the above required OPERABLE pump, shall be demonstrated inoperable"" at least once per 31 days, except when the reactor vessel head is removed, by verifying that the motor circuit breakers are secured in the open position.

T hgg,g May be ido Phna cI IO] /5c ky rage c h<> P<~P5 <FE<< >

foR. A peRi~ A F40 moRe ~AH ] QouA. ash I4 g~riplI a) r~-SeRviee gum pS ~ p(o <0<E A<rzahrho~s'a posi+i~e, QeAc4(v.+ ch~r yi'-s Wi e

~e~~,~~J duR,~) ~,s +i~e, 'I "A maximum of one charging/safety injection pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or 335oF/ ward the cleric,boa iressel head is i'laice.

equal'o

""An inoperable pump may be energized for testing provided the discharge of the pump has been isolated from the RCS by a closed isolation valve with power removed from the valve operator or by a manual isolation valve secured in the closed position.

~

SHEARON HARRIS - UNIT 1. 3/4 1-9

REAC IV TT PP(uOF A)~0 "Zi(BY t,'gPy CONTROL SYSTEMS

- $ 86 BORATED WATER SOURCE SHUTDOWN LIMITING CONDITION FOR'PERATION

3. 1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE:

a~ A boric acid tank with:

99oO A minimum contained borated water volume of QRS gallons, which is equivalent to kQ% indicated level.

(0%0

2. A minimum boron concentration of [7000] ppm, and T

3. , A minimum solution temperature of [65]4F.

b. The refueling water storage tank (RWST) with:

'Fg coo

1. A minimum contained borated water volume of [444405 gallons, whi ch i s equi val ent to ~V (P90 indi cated 1 eve 1 .

SCtvetu ArVd ~>++PP~

2. A ~inca boron concentration of [2000] ppm, and

3. A minimum solution temperature of [40]4F.

APPLICABILITY: MODES 5 and 6.

ACTION:

With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE RE UIREMENTS 4.1.2.5 The above required borated water source shall be demonstrated OPERABLE:

a0 At least once per 7 days by:

1. Verifying the boron concentration of the water,

2. Verifying the contained borated water volume, and

3. Verifying the boric acid tank solution temperature the source of borated water.

when it is

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when is the source of borated water and the outside air temperature is it less than [40]'F.

SHEARON HARRIS - UNIT 1 3/4 1-11

c REACTIVITY CONTROL SYSTEMS

'ORATED WATER SOURCES " OPERATING MAR $ 86 LIMITING CONDITION FOR OPERATION

3. 1.2.6 As a minimum, the foll'owing borated water source(s) shall be OPERABLE as requited by Specification 3. 1.2.2:

'a 0 A boric acid tank with:

] /goo A minimum contained'borated water volume of 44808 gallons, which is equivalent to 444 indicated level.

'f0'lo

'A minimum boron

2. concentration of [7000] ppm, and .

3. A minimum solution temperature of [65)

F.'he

b. refueling water storage tank (RWST) with:

y3(ohio

1. A minimum contained borated water volume, of [~88&3 gallons, which is equivalent to ~Sqgqo indicated t gives~

level.

~g gg~ p~~

2. A eea~e boron concentration of [2000] ppM

3. A minimum solution temperature of [40]4F, and

4. A maximum solution temperature of [125j'F.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

aO With the boric acid tank inoperable and being used as one of the above required borated water sources, restore the boric acid tank to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGIN equivalent to at least 2000 pcm. at 2004F; restore the boric acid tank to OPERABLE status within the next 7 days or. be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With the RWST inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SHEARON HARRIS - UNIT 1 3/4 1-12

SHi P>

P~y~ er ~ ~

PROOF AND REVIEN COPY POWER DISTRIBUTION LIMITS MN 88o LIMITING CONDITION FOR OPERATION ACTION Continued:

b. Within"'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside the above limits, verify through incore flux mapping and RCS total flow rate comparison that F~ and RCS total flow rate are restored to within the above 1imits, or reduce THERMAL POWER to less than 5X of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

C. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL'POWER limit required by ACTION a.2. and/or b., above; subsequent POWER OPERATION may proceed provided that F~ and indicated RCS total flow rate are through incore flux mapping and RCS total flow rate 'emonstrated, comparison, to be within acceptable limits to exceeding the following THERMAL POWER levels:

l. A nominal 50K of RATED THERMAL POWER,

2. A nominal 75K of RATED THERMAL POWER, and 3o Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95 of RATED THERMAL POWER.'URVEILLANCE RE UIREMENTS 4.2.3.l The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 F~ sha11 be determined to be within acceptable limits:

a. Prio~ to operation above 75K of RATED THERMAL POWER after each fuel loading, and

b. At least once per 31 Effective Full Power Days.

4.2.3.3 The indicated RCS total flow rate shall be verified to be within the acceptable limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months N ~ ~

4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months. The measurement instr~mentation shall be. calibrated within 7 days prior to the performance of .the calorimetric flow measurement.

4.2.3.5 The RCS total flow rate shall be determined by precision heat balance measurement SHEARON HARRIS at least

" UNIT 1 '/4 once per 18 months.

2-10

TABLE 3. 3-1 Continued REACTOR TRIP SYSTEM INSTRUHENTATION HINIHUH TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS 'IO TRIP OPERABLE MODES ACTION

12. Reactor Coolant Flow Low

a. Single 'Loop (Abpve P-8) 3/loop 2/loop in 2/loop in any oper- each oper-ating loop ating loop

b. Two Loops (Above P-7 and 3/loop. 2/loop in 2/loop 1 below P-8) two oper- each oper-ating loops ating loop

13. Steam Generator Mater 3/stm. gen. 2/stm. gen. 3/stm. gen. 1, 2 645m(l)

Level--Low-Low in any oper- each oper-ating stm. ating stm.

gen. gen.

14. Steam Generator Mater Level Low 2 stm.. gen. : 1 stm. gen. 1 stm. gen. 1. 2 Coincident Mith Steam/ level and level coin- ~

level and Flow Hismatch 'eedwater 2 stm./feed- cident with 2 stm-/feed-water flow 1 stm./feed- water flow mismatch in water flow mismatch in each stm. mismatch in same stm. gen.

gen. same stm. or 2 stm. gen.

gen. level and 1 stm./feedwater flow mismatch in same stm.

gen.

15. Undervoltage Reactor Coolant R/Pea>N 2 pe,ANT 1 68(1)

PUmps (jgbygg, p~7 2/pu p

TABLE 3. 3-1 Continued REACTOR TRIP SYSTEH INSTRUMENTATION MINIHUH TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE HODES ACTION

16. Underfrequency Reactor Coolant 2/qTIAi~ 2I Pumps (Above 'P-7)

17. Turbine Trip

a. Low Fluid Oil Pressure 3 68

b. Turbine Throttle Valve 4 108 Closure

18. Safety Injection Input from ESF 1, 2

19. Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, P-6 2

b. Low Power Reactor Trips Block, P-7

1) P-10 Input or

2) P-13 Input

c. Power Range Neutron

, Flux, P-8

d. Power Range Neutrons Flux, P-10 1 2

e. Turbine Impulse Chamber Pressure, P-13

TABLE 3. 3-3 Continued ENGIHEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION I

MINIMUM TOTAL HO. CHANNELS CHANNELS APPLICABLE g 'UNCTIONAL UHIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

3. Containment Isolation (Continued)

M 2) Automatic Actuation 1, 2, 3, 4 . 14 Logic and Actuation Relays

3) Containment See Item 2.c. above for Containment Pressure High-3 initiating Pressure High-3 functions and requirements.

y .9~

c. Containment Ventilation 40 Isolation

1) Manual Containment See Item 2,a. above for Manual Containment Spray initiating I Initiation functions and requirements.

6*4'7,

'pray Cl

2) Automatic Actuation .2 1, 2, 3, 4, 25 Logic and Actuation Relays

3) Safety Injection See Item l..above for all Safety Injection initiating functions and requirements. A<~

CL P~, tNIWW SSOhkaanr Sigma

4) Containment Radio" See Table 3.3-6, Item lr for Containment Radloectlofty~igh activity High initiating functions and requirements

5) Manual Phase "A" See Item 3.a.l) above for Manual Phase "A" Isolation initiating Isolation unctions and requirements.

PIERCC ua d6'at ~>~c{cpf +les ~of< so

"<Chai 4m.

Akmea~elS 4 +,~s ~~ "cL~Aids W+~iP" ~]~

R Q

TABLE 3.3-4 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS I

SENSOR TOTAL ERROR M

FUNCTIONAL UNIT ALLONANCE TA Z ~S TRIP SETPOINT ALLOUABLE VALUE EIT

6. Adxiliary Feedwater (Continued)

g. Steam Line Differential 5.0 1.47 3.0 < '100psi < 127.4 psi Pressure High Coincident With: See Item 4. above for Main Steam Line Isolation Trip Setpoints Main Steam Line Isolation and Allowable Values.

7. Safety Injection Switchover to y TIOO

. Containment Sump o

a. Automatic Actuation Logic and Actuation Relays .

N.A. N.A. N.A. N.A. N.A.

g CA

'll

)

23.'f

b. RMST Level Low-Low '.A. N.A. N.A. > [08e43X Coincident With See Item l. above for all Safety Injection Trip Setpoints and Safety Injection Allowable Values.

8. Containment Spray Switchover to Containment Sump

a. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.

'nd Actuation Relays

b. RMST"-Low-Low See Item 7.b. above for all RMST Low-Low Trip Setpoints and Al 1 owabl e Values.

Coincident Mith: See Item 2. above for all Containment Spray Trip Setpoints Containment Spray and Allowable Values.

9 R

- Ti Q)

TABLE 3.3-4 Continued

~X

'J$ K ENGINEERED SAFETY FEATURES ACTUATIOH SYSTEM IHSTRUMENTATIOH TRIP SETPOINTS ) 0 0

SENSOR TOTAL ERROR gpss FUNCTIONAL UNIT ALLOWANCE TA Z ~S) TRIP SETPOIIIT ALLOWABLE VALUL T~)Ro a

9. Loss-of-Offsite Power s

9gfn ~ rrs$fO aTOI<5 Pi~4 a 6.9 kV Emergency Bus N.A. N.A. N.A. > [4048] >,.f4993 volts

~

Undervoltage Primary volts with with a ~%&3 a < fl.0] f time second time del ay bc~'" SCcoodS EI,Q $ pIosd IX s-

,delay.

Otal 2'f rtsgoo

b. 6.9 kV Emergency N.A. N.A. N.A. .> [&S&) volts > [408k] volts Secondary Bus.'ndervoltage with a /ED second time>'~

with see~f a <~$

time

)

delay (with~ delay with+et Safety Safet~ '~<< I Vhsscf PO'<Co~d S Injection). Injection).

6'IZV 4,VW

[44N3 volts . > [489&] volts with a < f54. 0] with a <

second time second time

[~) z g7g delay (withdI~+ delay (without Safety Safety Injection). Injection).

10. Enginee'red Safety Features Actpation System Interlocks

a. Pressurizer Pressure, P-ll N.A. H.A. H.A. > [2000] psig > [19e6] pslg

b. Low-Low T, P-12 N.A. N.A. N.A. > [553] F . > [550.6]'F Trip, P-4 avg'eactor C. H.A. N.A. N.A. N.A. H. A.

Steam Gener ator Water Level, See Item 5.b above for all Steam Generator Water Level Trip SetpoiIIts P-14 and Al lowable Values.

RFVISION l'Itoof QP LBlN NR SSS TABLE 3.3-5 Continued LOB'NGINEERED 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 Driven < [60]

Pumps F

6) Emergency Service Hater Pumps < t:32](')/t:22]( '

7) Containment Fan Coolers < $ 27](1)/t:17]<)

8) Control Room Isolation N.A.

4. Hain Steam Line Pressure Low "

a. Safety Infection (ECCS) < I:12] /(22]

1) Reactor Trip < t2]

2) Feedwater Isolation < p7](3)

3) Containment Phase "A" Isolation t~(2)/t~j(1)

4) Containment Ventilation Isolation (6)

5) Auxilfary Feedwater Motor Op'fven < f60]

Pumps t F

6) Emergency Service Mater Pumps $ 32](+)/f22](~)

7) Containment Fan Coolers < p7](1)/$ 17](g

8) Control Room Isolation

b. Steam Line Isolation

5. Containment Pressure<<-High-3 rF.S

a. Containment Spray < [4e4er j(+)/[32.2j

b. Phase "B" Isolation < $ 22.5]( )/t:12]

6. Containment Pressure High-2 Steam Line Isolation <<7]~

g~~vc

7. ~ Steam Line Pressure - QeyeAe Rate High

~

Steam Line Isolation < pj~

SHEARON HARRIS - UNIT 1 3/4 3-35

SHNPP Afl3 IiBlB COPY RpVic; Inc >

PAQQF

~

gg 586 TABLE 3.3-5. Continued ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL ANO FUNCTION RESPONSE TIME IN SECONDS

8. Steam Generator Mater Level""High-High

a. Turbine Trip < [2.5$

b. Feedwater Isolation <7~(3)

9. Steam Generator Mater Level Low-Low

a. Motor-Driven Auxiliary < E603 Feedwater Pumps

b. Tur bine-Driven Auxi1 iary < f603 Feedwater Pump

10. Loss-of-Offsite Power w~~ ~~~ Turbine-Driven Auxiliary Feedwater Pump < f60)

Trip of All

~

~~g.

Main Feedwater DRLvc&

Auxiliary Feedwater Pumps Pumps N.A.

Steam Line Differential Pressure-High

~

Coincident with Main Steam Line Isolation Signal Isolate Auxiliary Feedwater to the I: N.A. g Affected Steam Generator

13. RWST Level Low-Low a~ Safety Injection Switchover to < [323 Containment Sump Coincident with Safety Injection ~

b. Safety Injection Switchover to < 51033 Containment Sump Coincident With

'ontainment Spray 14..

4sohaUaa ddi ii ili 5](6>7) a-. CDWm~~c~f P~n)e Xsota+r~

SHEARON HARRIS - UNIT 1 3/4 3-36

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM IHSTRUHENTATIOH SURVEILLANCE RE UIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR MHICH CHANNEL CHANNEL CHANNEL, OPERATIONAL OPERATIOHAL ACTUATION RELAY ";

RELAY SURVEILLAHCl FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LMI TEH TE T . YE Y REtE

3. Containment Isolation (Continued)

3) Containment S N.A. H.A. H.A. N.A. 1, 2, 3 Pressure High-3

c. Containment Ventilation

~

~ ~c, Isolation

'Q c

1) Manual Containment See Item 2.a. above for Manual Containment'Spray Surveillance Requirements.

Spray Initiation "P5

2) Automatic Actuation H.A. H.A. . H.A. H.A. M(l, 2) M(1, 2) g(2) 1, 2, , 4, Logic and Actuation 68 Relays

3) Safety'njection See Item l. above for all Safety In)ection Surveillance Requirements.

4) Containment See Table 4.3-3, Item Q, for Containment 4a~~v44y~~

g~gQ~ 2'sr'+.e~ ~~(

Surveillance Requirements gg~ ~,g Radi oacti vi ty High A

5) Manual Phase A See Item 3.a.l) above for Manual Phase A Isolation Surveillance Requirements.

Isolation

4. Main Steam Line Isolation

~

a. Manual Initiation H.A. H.A. N.A. -H.A. N.A. N.A. 1, 2, 3

b. Automatic Actuation H.A. H.A N.A. M(1) M(1) q 1,2, 3 Logic and Actuation Relays

c. Containment Pressure S N.A. N.A. N.A. N.A. 1,2, 3 High-2

RR/tc;la~i TABLE 3. 3-8 P800F AHO EISlBI MPY METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM INSTRUMENT LOCATION OPERABLE

1. Wind Speed Nominal Elev. 12.5 meters Nominal Elev. 61.4 meters

2. Wind Oirection Nominal Elev. 12.5 meters Nominal Elev. 61.4 meters

3. Air Temperature Differential Temperature 11.0 meters ~59;9 meters SHEARON HARRIS - UNIT 1 3/$ 3-54

SHNPP- PROOF A'$D RPtIEI Capy INSTRUMENTATION PP $ (f ~%) ~a ~

FIRE DETECTION INSTRUMENTATION MAR 3986 LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3"ll shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTION:

With any, but not more than one-half the total in any fire zone, Func-tion A fire detection instruments shown in Table 3.3-11 inoperable, restore the inoperable instrument(s) to OPERABLE status within 14 days or within the next 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6. 1.5).

b. With more than one-half of the Function A fire detection instruments in any fire zone shown in Table 3.3-11 inoperable, or with any Func" tion B fire detection instruments shown in Table 3.3-11 inoperable, or with any two or more adjacent fire detection instruments shown in Table 3.3-11 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is located inside the containment, then iaspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (or moni" tor the containment air temperature at least once per hour at the locations listed in Specification 4.6. 1.5).

C. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

~ \

SURVEILLANCE RE UIREMENTS 4.3.3.8. l. Each of the above required fire detection instruments which are during plant operation shall be demonstrated OPERABLE at least once 'ccessible per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST~ Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST+during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

4.3.3.8.2 The NFPA Standard 72D supervised circuits supervision associated with the detector alarms of each of the above required fire dete'ation instruments shall be demonstrated OPERABLE at least once per 6 months.

~ Se+poi~fs 4oa Hew< R~J I-/41 e Je+eeh,zs <e~ ~,4 he H

ueei4leJ. ~ f'"

4o< S~oke 'defeefons shoa lt be. vel'if~ed oa <@cay de.eR Pasd va/.

SHEARON HARRIS - UNIT 1 3/4 3-65

PROOF AND PB)P(V COPY 8 Hi" P P TABLE 3. 3-11 ConAKRd RPJjSjQt ~

FIRE OETECTION INSTRUMENTATION NR 11m TOTAL NUMBER OF INSTRUMENTS ELEVATION HEAT FLAME SMOKE ZONE INSTRUMENT LOCATION ~FT ~A/B * ~A/B * ~A/B *

2. 0 Reactor Auxi 1 i a Buil din Continued g4.

1-A-4"CHLR HVAC Chiller Equipment Area 261. 0 0/.4d .42/0 8 Cable Trays Coh-8 1-A-4-PlNf Boric Acid Equipment Area 261. 0 0/12 13/0 4 Corridor Cable Trays cow@

1-A-4/ME Corridor Cable Trays 261. 0 0/g 12/0 Cdd-I 1"A-4-CQC Corridor Cable Trays 261. 0 0/4' 7/0 1-A-4-CHFA Charcoal filter Room 1A 261. 0 0/5 10/0 1-A-4-CHFB Charcoal Filter Room 1B 261. 0 o/4 8/0 1-A"EPA Electrical Penetration Area SA 261. 0 -O/15 15/0 1-A-EPB Electrical Penetration Area SB 261. 0 0/15 15/0

/-1-S -P'V8 S~~~eae~ Resow 4 W-/P. DuCr zBC.O 8/o 1-A-5-HVA

/-g -g-k va 1-A-5-HVB HVAC Room 1A Satimraaeg HVAC Room 1B

~ 3 A///> >~<

286. 0 2'Bd, o 286. 0 14/o P/o 15/0

/-A-s'- N8 1-A-MRA ALee~c Sw~v Switchgear 5-9A j HE suer 884.d 286. 0 w/o Room A 18/0 1-A-MRB Switchgear Room B 286. 0 17/0 1"A-BATA Battery Room 1A 286. 0 2/0 1-A-BATH Battery Room 1B 286. 0 2/0 27 27 1-A-CSRA Cable Spreading Room A 286. 0 0/g pX/0 1-Jf-CSRB Cable Spreading Room 8 286. 0 0/15 15/0 1-A-ACP Auxiliary Control Panel 286. 0 2/0 t-Cl-C~RA P~C %em A ZB.o 2/O 12-A-6-RT1 Terminal Cabinet Room 305. 0 14/O Rod Control Cabinets Room

'2-A-6-RCC1 305. 0 <g/0 gplhl 12-A-6-CR1 Control Room Adea 305. 0 ~ +/0 12-A-6-APRl Auxi1 iary Relay Panel s 305. 0 6/0 jz-A-&-col Co~~< go~ PA~ecs 305.o 9/o

)g-8 gV SHEARON pfyS Vavn<y~d HARRIS - UNIT 1 Acr 0-P/ 3/4 3-67 3'. 0 !/g

'SHNPp PROOF Ai"0 PE;.~"E>'l t',O'Y 8 -V$ Sit. '.I Tab 1 e 3. 3-11 Continued',

TOTAL NUMBER OF INSTRUMENTS ELEVATION HEAT F LAME SMOKE INSTRUMENT LOCATION ~FT ~A/8 * ~A/8)" (A/8)"

2. 0 Reactor Auxi 1 i a Bui 1 din Continued 12-A-6-PICR1 Process Instruments & Control 305. 0 s/o

,ja g( Racks e/o l? R $ j/1) 0 coHTjpoc Ann Pgifc AA '/Z Qcr Zcu. 0 c )y ~) gC 12-A-6-HV7 HVAC Eauipment Room ccEcrAltgc. aquiAesvr fm7PeTlod 305. 0 0/4'8 zyg/0

//y7 z/o z/o "F-2-FPC Fuel Pool Cooling Pumps & 236. 0 O/16 Heat Exchangers 5-F-3-CHFA . Emergency Exhaust Charcoal 261. 0 o/8 8/0 pv'zer 1 Filter A t

/N< 5-F-3-CHFB Emergency Exhaust Charcoal Z61. 0 0/8 8/0 Filter B 5-F-3-CHF-BAL Emergency Exhaust Bal ance <<<<<<4/0 5 .'S.l<<"IZ elar 4.0 Diesel Generator Buildin

<<<<<<<<A<< Z61. 0 Z&J 0~ i Z./n 4

'61.0 p/0 1-0-1-OGA-RM Diesel Generator 1A o/1o 1-0-1-OGB-RM Diesel Generator 1B 261. 0 O/1O 4;8/0 Diesel Generator Air Starting 261.0 2/o 1-0"1-OGA-ASU'-0-1-DGB-ASU Unit 1A Diesel Generator Air Starting 261. 0 2/0 Unit 1B

. 1-0-1-DGA- TK Diesel Fuel oil Oay Tank lA 280. 0 1-0-1-OGB-TK Diesel Fuel Oil Day Tank 1B 280. 0 1.-0-1-QGA-ER Diesel Generator MCC & Control 261. 0 2/0 Panel 1A 1-0-1-QGB-ER Diesel Generator MCC & Control 261.0 2/0 Panel 1B 1-0-3-OGA-ES Diesel Exhaust Silencer 1A 292. 0 2/0 1-0-3-QGB" ES Diesel Exhaust Silencer 1B 292. 0 2/0 i"b-3.pAO.Ã4 Zi.tutrix A~Nnoe'on R /INC vv

. Q-g 292,O ajo NS.N Ekgc7ltiofa EwrnQr Peen P PIC Ncv'+4-z9z. 0 <//o SHEARON HARRIS -%IT 1 3/4 3-68

po grig@ Sv~Pc r Puc~ Ah'-ZZA,'H'~25 24/ 0 Porqn~c Saucy 5'vcr gjf-fg f gP'XP'25. ~

Awnac. GPPc y 5~r Ag'Xg f gd'Qj'ZP'.0 I

Coedu~g j'onnuNic'pl77i4 4 kioA Pgc, /~der 4P-1r"A,ek'-)7Z zan o -- --- lo I 2 Con/vaR I+77ZgY f AVE Hno&IC'u~

dan. 4 Q c Tio 80~S HV8C 2>c->

f Hp -/ST

t PBDOF AjIO IIEVIESY COPY JiSIQN TABLE 3.3-11 Continued}

<NR . $ 86 TOTAL NUMBER OF INSTRUMENTS ELEVATION HEAT FLAME SMOKE ZONE INSTRUMENT LOCATION FT '~A/8 * ~A/8 * (A/8)"

5.0 Oiesel Oil Storm e Tank Area I"0-PA Diesel Fuel Oil Pump Room IA 242.25 0/2 2/0 1-0" PB Oiesel Fuel Oil Pump Room 18 242.25 0/2 2/0 5"0-BAL Oiesel Fuel Oil Storage Tank 242. 25 7/0 m<<w Area Balance 6.0 Emer enc Service Water Intake Structure 12"1-ESWPA Electrical Equipment Room SA 251. 7/ 9'0/0 262. 0 Pump Room SA 262. 0 2/0 12-1-ESWPB Electrical Equipment Room SB 25I. 7/ 10/0 262. 0 Pump Room SB 262.0- 2/0 yP,('g

">/q SHEARON HARRIS - UNIT 1 3/4 3-69

r TABLE 9.3"Ila

':,ii

'" f f',!.Pi'I~I)]"

HVAC DUCT FIRE DETECTION INSWUHWTS (, ~ ') >> ) a a l

Sup y Fan Smoke Detector Zone HVAC S stem Tag No.

1.0 Rea tor huxilia Buildin I V 1-A-5-HVA S~itchgear Room A FAD-1FP-8655-A01 EL. 286 AH-12 (1A-SA),,(1B-SA) FAD-1FP-8655-A02 FAD-1FP&65$-A03 v 1-A-5-HVB itchgear Room B FAD-1FP&655-BOl EL. 286 3 (lA-SB) (1B'-SB) FAD-lFP-8655-B02 FAD-1FP&655-B03 FAD-1FP-8655-B04 V 12-A-6-HV7 Electri 1 Equipment FAD-IFP&655-C01 SHg pp EL. 305 Pz'otecti Rooma FAD-1FP&655M02 HVAC AH-16 (IA-SA) REVtsfON

'1B-SB)

MAR ~986

~2-A-7-HV NNS Ventilatio FAD-1FP-8655-DOl EL. 324 AH-14 (NNS) j'AD-1 FP-8655-D02 FAD-1FP-8655-D03 !

FAD-1FP-8655-D04!

/

1-A-5-HV3 Norma1 Supply . FAD-1FP&655-EOl EL 286 s-3A (NNs) s-,3B (NNs) FAD-lFP&655-E02, FAD-1PP&655-E03 AD-1FP&655-E04 1FP& 655-E05 I

y'2-AW-HV7 ControX Room HVAC F 1FP-8655-F01 EL. 305 AH-aSj(1A-SA), (1B-SB) FAD- FP-8655-F02

-ee>5-Fu3 FAD-aF 8655-FO4 (Later) mputer 6 Communication FAD"1FP-8 55-G01 EL. 324 RH HVAC AH-97h(NNS) FAD-lFP-86 5W02 AH-97B(NNS )

(Later) Computer Battery 6 Aux FAD-1FP-8655- 1 EL. 324 Electric Protection Rma FAD-lFP&655-H HVAC hH-98A ')".'&),

hi) -. 'ih ( NNS )

2.0 Fuel Handling Building V 1 AW-CHFA Normal Supply (South) FAD-1 FP-8 657-AOI

-L. 261 'H-21h (NNS}, k'ILD-Ik )'-ebb 7-A02 AH-21 B (hNS )

86768

~l

i ABLE 0~ 0 HVhC DUCT FIRE DETECTION JNSTRU~l'TS Supply Fan Smoke Detector Zone ~

HVAC S stem Tag No.

y/

2.0 Fuel Hand)An 8~odin (Conn'd) 5-F-3-HV L Noanal Sup 7 (Norah) FABFIFP 86-57 80-1

+ EL. 261 AH-22A (NNS), FADa-1FP&657-B02 AH-22B (NNS)' yFAD-1FP&657-B03 12-A-7-HV

+ EL. 324 Normal Supply (Oper'Fl'K AH-56 (NNS),

AH-57 (NNS)

~ FAD-IFP&657-C01 FAB-1FP-8657-002

/12%-7-HV Normal Suppl Oper Fl) FAD-IFP-8657-D01 ZL. 324 AH-58 (NNS) F~FP&657-D02 AH-59 (NN 3.0 Diesel Generator uildi

~l-D-3-DCA-HVR Ely tric Equip. FAD-IFP-8658 boa EL. 292 Rm. A HVAC AH&58 . FAD-1FP&658-~

lA-SA), AH&5 (1B-SA) 1-D-3-DGB- VR Electric Equip FAD-1FP&658-B01 EI 292 Rm B HVAC FAD-1FP-8658-B02 AH&5,(1AWB),

AH&5 (1BWB) 8676g Qp piC I 4'IBT g/4. - 3-(r>E

TABLE 4.3-9 Continued m

Sa RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS

])(g zrA.

CD CHANNEL MODES FOR NlICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE INSTRUMENT CIIECK CIIECK CAKIER EIRE TE I IC REISIRED

'. WASTE PROCESSING STACK 5 BUILDING VENT a.f. Noble Gas ActivityW+<<<<~ot Honitor(<<C) D R(3) gable Cae Ac4<e<ty (QR4%) >

b. Iodine Sampler M N.A. N.A.

c. Particulate Sampler N.A. N.A. N.A.-

d. Flow Rate Monitor N.A.

e. Sampler Flow Rate Monitor N.A. qN tab

5. MASTE PROCESSING BUILDING VENT STACK 5A

a. Noble Gas Activity Honitor R(3)

b. Iodine Sampler ~ aA. N;A. N.A. N.A.

c; Particulate Sampler ~u,A. N.A. N.A. N.A.

d., Flow Rate Monitor ~

N.A.'.A.

-e. Sampler Flow Rate Monitor rn

PRDQF AND RPttP(Y COPY RF..Vi3iQI'j 3/4." ":MERGENC. "ORE COOLING S S EMS 3/4.5. 1 ACCUMULATORS COLO LEG INJECTION LIMITING CONDITION FOR OPERATION 3.5.1. Each Reactor Coolant System (RCS) accumulator shall be OPERABLE with:

a. The isolation valve open,

b. A contained borated water volume of between 66 and 97K level.

2 zocl IAAJSCh&4

c. A boron concentration of between I.1900] and L~] ppm, and

d. A nitrogen cover-pressure of between I:585] and L665] psig.

APPLICABILITY: MOOES 1, 2, and 3"..

ACTION:

'a 4 With one accumulator inoperable, except as a result of a closed isolation valve, restore the inoperable accumulator to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With one accumulator inoperable due to the isolation valve being closed, either immediately open the'isolation valve or be in at least HOT STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE UIREMENTS 4.5.1.1 Each accumulator shall be demonstrated OPERABLE:

'a 0 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1. Verifying, by the absence of alarms, the contained borated water volume and nitrogen cover"pressure in the tanks, and

2. Verifying that each accumulator isolation valve is open.

"Pressurizer pressure above 1000 psig.

SHEARON HARRIS " UNIT 1 3/4 5-1

3H PP Ni Pt":g )~3-'~t'I PROOF APJO AEVIEY/ COPY EMERGENCY CORF COOLING SYSTEMS MAR $ 986 SURVEILLANCE RE UIREMENTS Continued)

CP8(L EBASCO Valve No. Valve 8o. Valve Function Valve Position" f]k'SI-107 2SI"V500SA-1 High Head Safety Injection to Closed"1 Reactor Coolant System Hot Legs X/Si-S6 2SI-V501SB-1 High Head Safety Injection to Reactor Coolant -System Hot Legs ipse-52 ZSI-V502SA-1 High Head Safety Injection to Closed-1 Reactor Coolant System Cold Legs fgSI-340 2SI-V579SA-1 . Low Head Safety Injection to Open"1 Reactor Coolant System Cold Legs ggSI-341 2SI"V578SB-1 Low Head Safety Injection to Open-1 Reactor Cool'ant System Cold Legs XII"359 2SI-V587SA-1 Low Head Safety Injection to Closed"1 Reactor Coolant System Hot Legs

b. At least once per 31 days by:

1. Verifying that the ECCS piping is full of water by venting accessible discharge piping high points, and

2. 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.

C. By a visual inspection which verifi.es that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:

For all accessible areas of the containment prio~ to establish-ing CONTAINMENT INTEGRITY, and

2. Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.

"Closed-1 and Open-1 The Control Power Oisconnect Switch shall be maintained in the "OFF" position and the valve control switch shall be maintained in the valve position noted above.

SHEARON HARRIS - UNIT 1 3/4 5-4

PAOQF Ai,'0 narlBv c;;Y EMERGENCY CORE COOLING SYSTEMS

>i vV SURVEILLANCE RE UIREMENTS Continued V HPSI SYSTEM HPSI SYSTEM HPSI SYSTEM EBASCO Valve No.(FSAR) .EBASCO Valve No. CPCL Valve No.

25 I-V16SA-1 2SI-V440SA-1 XZSI-5 2SI-V22SB-1 2SI-V439SB-1 5 XSI-6 2S I-V28SA-1 2SI-AS6& +gap sh-l XII-7 2SI-V62SA-1 2SI-V437SA-1 ggSI-69 25 I-V68SB-1 ~

2SI-V436SB-1 ggSI-70 2S I-V74SA-1 25 I-V435SA-1 g gSI-71 2SI-V38SA" 1 2SI"V434SA-1 SXSI-101 2S I-V44S8-1 2SI "V433SB-1 8 lSI-102 2SI-V50SA-1 2SI-V432SA-1 SlSI-103 2SI-V83SA-1 2SI-V431SA-1 ggSI" 124 2SI-V89S8-1 2SI-V430SB"1 4 gSI-125 2S I-V95SA-1 , 2SI-V429SA-1 XQSI-126

h. By performing a flow balance-t'est; during'shutdown, following com-pletion of modifications to the ECCS subsystems that alter the subsystem flow characteri sti cs and verifying that:

1. For charging/safety injection pump lines, with a single pump running:

a) The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 379 gpm, and b) The total pump flow rate is less than or equal to 650 gpmo

2. For RHR pump lines, with a single pump running, the sum of the injection line flow rates is greater than or equal to 3663 gpm.

SHEARCN HARRIS - UNIT 1 3/4 5-6

PROOF AHO Rt~ilEN COPY 8ptqH i>~ ~" P EMERGENCY CORE COOLING SYSTEMS p] ~

3/4.5.4 REFUELING WATER STORAGE TANK LIMITING CONOITION FOR OPERATION 3.5.4 The refueling water storage tank (RWST) shall be OPERABLE with:

yet,ooa

a. A minimum contained borated water volume of QhQSOOO] gallons, which b.

qgyy ~~

is equivalent to 40'ndicated level.

A eierieee boron concentration of [2000] ppm

~~~~, Pud ~ Pi

c. A minimum solution temperature of [40]4F, and

d. A maximum solution temperature of [125] F.

APPLICABILITY: MOOES 1, 2, 3, and 4.

ACTION:

With the RWST inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT'STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.5.4 The RWST shall be demonstrated OPERABLE:

a. At least once per 7 days by:

l. - Verifying the contained borated water volume in the tank, and

2. Verifying the boron concentration of the water.

b. At least once. per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when the outside air temperature fs less than 40'F or greater than

[125]4F.

SHEARON HARRIS - UNIT 1 3/4 5-9

SHgpp

>FVrSy <<

PHQOF AtJO REVIEW COPY MAR j986 CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION ANO COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM

/u '-

LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with. each Spray System capable of taking suction from the RWST and transferring suction to the containment sump.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With one Containment Spray System inoperable, restore the inoperable Spray System to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable Spray System to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN wi'thin the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Refer to Specification 3.6.2.3 Action. 'lso SURVEILLANCE RE UIREMENTS 4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:

'i

a. 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. By verifying, that on recirculation flow, discharge pressure of greater than or equal to tested pursuant to Specification 4.0.5;

~

each pump develops a Zf8 psig when C. At least once per 18 months during shutdown, by:

to its correct position on"containment spray actuation ~

Verifying that each automatic valve in the flow path actuates test signal and

2. Verifying that each spray pump starts automatically on a containment spray actuation test signal.

d. At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

'Va<<P'1'+ ~~~pypg ~ogcua~ rioA at84.VE'gOA &E, 4'uAP

~~~~~ ~ ad W$ 7 h-Eo yrsrss SHEARON HARRIS " UNIT 1 3/4 5-11

BH(<J pp PFQQF hiJ9 flBiBi ~0py PF~j <, ~~< ~ ~

CONTAINMENT SYSTEMS 3/4. 6. 3 CONTAINMENT ISOLATION VALVES MAR ]985 LIMITING CONDITION FOR OPERATION

.LETh OPERABLE i

with isolation times i 1 i 1 as shown in I ifidi ~h11 APPLICABILITY: MODES 1, 2, 3, and 4 Mith one or more of the containment isolation valve(s) specified in

~ ~ ~ ~ ~

~

inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:

a. Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or

b. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured 'in the isolation position, or

c. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange, or in at least HOT STANDBY within the next

~

d. Be 6 hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS'e'Tcchu<col

~e< <<1~<+4 Egu<p<<<tet L<s+ 'PRof eA if'

.6.3.1 Th t 1 i 1 p t i1 d OPERABLE prior to returning'the valve to service after maintenance, repair or replacement work is performed on the vilve or its associated actuator, control or power circuit by performance of a cyc't'ing test, and verification of isola-tion time.

+gate z~eA.c'1 6y 9, 7. I 5 pf'A5 O'S

'/4 I

SHEARQN HARRIS - UNIT 1 6-14

PROOF IID REVIEN COPY ELECTRICAL POWER SYSTBlS HNPP A.C. SOURCES tsar v OPERATING QR $ 86 LIMITING CONDITION FOR OPERATION ACTION Continued:

Statement based on the time of initial loss of the remaining inoper-able diesel generator. A successful test of diesel OPERABILITY- per Surveillance Requirement 4.8.1.1.2.a.4 performed under this Action Statement for a restored to OPERABLE diesel satisfies the EDG test requirement of Action Statement b.

SURVEILlANCE.RE UIREHENTS 4.8.1.1.1 Each of the above required physically independent circuits between the offsite transmission network and the onsite Class lE distribution system shall be:

~dy

a. Determined OPERABLE

' at least once per 7 days by verifying correct breaker alignment and 8 88818111 1 8 18 8 manually transferring the onsite Class 1E power supply from the unit' auxiliary transformer to the startup auxiliary transformer.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a. In accordance with the frequency specified in Table 4.8. 1 on a STAGGERED TEST BASIS by:

1. Verifying the fuel level in the day tank.

2. Verifying the fuel level in the main fuel oil storage tank.

3. Verifying the fuel oil transfer pump. can be started and transfers fuel from the storage system to the day tank.

4. Verifying the diesel generator can start"" and accelerate to synchronous speed (450 rpm) with generator voltage and frequency 6900 t 690 volts and 60 + 1.2 Hz. Subsequently, verifying the generator is synchronized, gradually loaded"" to an indicated 6200-6400 kM""" and operates for at least '60 minutes.

4pgalf Wc pvcc5$ ulc M A4 i+psl otic 4lg sf'+ ~cceiv4A f/CCQAR +Alt/ Ok 4g4h I + flA&7 P5tf 8

""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.

HARRIS - UNIT 1 'HEARON 3/4 8-3

PROOF AIjO HE'AYA'OPY REFUELING OPERATIQ4S 3/4.9.12 FUEL HANDLING BUILDING EMERGENCY EXHAUST R~tc,inn,i MAR I86 LIMITING CONDITION FOR OPERATION 3.9.12 Two independent Fuel Handling Building Emergency Exhaust System Trains shall be OPERABLE.

APPLICABILITY: Whenever irradiated fuel is in a storage pool.

ACTION:

Mith one Fuel Handling Building Emergency Exhaust System Train inoperable, fuel movement within the storage pool .or crane operation with loads over the storage pool may proceed provided the OPERABLE Fuel Handling Building Emergency Exhaust System Train is capable powered from an OPERABLE emergency power source and is in of'eing operation and discharging through at least one train of HEPA filters aod charcoaI adeorber/

b. Nth no Fuel Pandling Building Emergency Exhaust System Trains OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with 'loads over the storage pool unti'1 at least one Fuel Handling Building Emergency Exhaust System Train is restored to OPERABLE status.

Ce The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.9.12 The above required Fuel Handling Building Emergency Exhaust System trains shall be demonstrated OPERABLE':

a. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room,'lowethrough the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating;

b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system by:

1. Yerifying that the cleanup system satisfies the'in-place penet) ation and bypass leakage testing acceptance criteria of less than f0.05%3 and uses the test procedure guidance in Regulatory Positions C. 5. a, C.5. c, and C.5. d of Regulatory Guide 1.52, Revision 2, March 1978, and the unit flow rate t

is $ 6600) cfm 10%

SHEARON HARRIS - UNIT 1 . 3/4 9-14

TABLE 3.12-1 Continued RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM HUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AHD SAMPLIHG AHD TYPE AHD FRE(UEN( )

AHD/OR SAMPLE SAMPLE LOCATIONS( COLLECTION FREIlUEHCY OF ANALYSIS

4. Ingestion (Continued)

S,u~Ash

b. Fish and One sample of~ey84s-, Cat- Sample in season, or Gamma isotopic analysis Inverte- fish, and Large-Mouth Bass semiannually if they on edible portions.

br ates species in vicinity of plant are not seasonal.

discharge area.

One sample of same species in areas not influenced by plant discharge.

c. Food Samples pf three different Monthly during Gamma isotopic (4) and I-131 Products kinds of broad leaf vegeta- growing'season. analyst s.

tion grown nearest each of two different offsite loca-tions of highest predicted annual average ground level D/g if milk sampling is not performed.

One sample of each of the Monthly dur ing Gamma isotopic and I-131 similar broad leaf vegeta- growing season. analysis.

tion grown 15 to 30 km dis-tant in the least prevalent wind direction if milk sam-pling is not performed.

Rex N+

I o

QP~)~~P PROOF AHO 8>'tEN 0CJ P REACTIVITY CONTROL SYSTEMS BASES MODERATOR TEMPERATURE COEFFICIENT Continued within its Iim'its" since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.

3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant. System average temperature less than t:551] F. This limitation is required to ensure: (1) the moderator temperature coefficient is within it analyzed temperature range, (2) the trip instrumentation is within its normal operating range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (4) the reactor vessel is above its minimum RTNDT temperature.

3/4.1. 2 BORATION SYSTEMS The Boron Injection System ensures that negative reactivity control is available.

during each mode of facil'ity operation. The components required to perform this function include: (1) borated water sources, (2) charging/safety injection pumps, (3) separate flow paths, (4) boric acid transfer pumps, and (5) an emergency power supply from OPERABLE diesel generators.

With the RCS average temperature above 200'F, a minimum of two. boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable. The boration capa-bility of either flow path is sufficient to provide a SHUTDOWN MARGIN from expected operating conditions of 1770 pcm after xenon decay and cooldown to 200pF. The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and require 46888 gallons of t'70003 ppm borated water be maintained in the boric acid storage tanks or [~803 gal-lons of 2000 ppm borated water be maintained in the refueling water storage'3g opp tank (RWST). / QQ'00 With the RCS temperature below 200 F, one boron injection flow path is accept-able without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single boron injection flow path becomes inoperable.

The limitation for a maximum of one charging/safety injection pump (CSIP) to be OPERABLE and the Surveillance Requirement to verify all CSIPs except 'the required OPERABLE pump to be inoperable below [3354F] provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

capability required below 200 F is sufficient to provide a SHUTDOWN The boron condition requires either ~

MARGIN of 1000 pcm after xenon decay and cooldown from 200 F to 140'F.

gallons of t:7000] ppm borated water be in the boric acid storage/tanks or t.~4%&) gallons of 2000 ppm borated water be This maintained maintained in 'the RWST. / 72,oat SHEARON HARRIS - UNIT 1 B 3/4 1-2

SHWF P A80 HKVfB'k CONTAINMENT SYSTEMS A~lc,inc,i PROOF COPY NR 586 BASES 3/4. 6.1. 5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the safety analysis for a [LOCA or steam line break acci-dent]. Measurements shall be made at all listed locations, whether by fixed or portable instruments, prior to determining the average air temperature.

3/4.6.1. 6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will.

withstand the maximum pressure of 41 psig in the event of a postulated main steam line break accident; A visual inspection in conjunction with the Type A leakage tests is sufficient to demonstrate'-this capability.

3/4.6.1. 7 CONTAINMENT VENTILATION SYSTEM The 342-inch3 containment preentry purge makeup and exhaust isolation valves are required to be sealed closed during plant operations since these valves have not been demonstrated capable of'closing during a )LOCA or steam line break accident). Maintaining these valves sealed closed during plant operation en-sures that excessive quantities of radioactive materials will not be released V1a the Containment Purge System. To provide assurance that these containment ives cannot be inadvertently opened, the valves are sealed closed in accord"

~] ance with Standard Review Plan 6.2.4 which'ncludes mechanical devices to seal or lock the valve closed, or prevents power from being supplied to the valve operator.

Py~b The use of the<containment purge lines is restricted to the [8-inch] purge makeup and exhaust isolation valves since, unlike the [42>>inch7 valves, the f8-inch3 valves are capable of closing x/uring a [LOCA or steam line break acci-dent). Therefore, the SITE BOUNDARY dose guideline of 10 CFR Part 100 would not be exceeded in the event of an accident during containment PURGING opera-tion. p The total time the containment purge system iso" lation valves may be open during MODES 1, 2, 3, and 4 in a calendar year is a function of anticipated need and operating experience. Only safety-related reasons; e.g., containment pressure control'or the reduction of airborne radio-activity to facilitate personnel access for surveillance and maintenance activ" ities, may be used to support s ~

the opening of these isolation valves during MODES 1, 2, 3, and 4, Leakage integrity tests with a maximum allowable leakage rate for containment purge makeup and exhaust supply valves will provide early indication of resil-ient material seal degradation and will allow opportunity for repair before SHEARON HARRIS - UNIT I B 3/4 6-2

PHDOF AND REVIDIt CavY PLANT SYSTEMS BASES AUXILIARY FEEDMATER SYSTEM Each electric motor driven auxiliary feedwater pump is capable of delivering a total feedwater flow of [450) gpm at a pressure of t:1170j psig to the entrance of the steam generators. The steam-driven auxiliary feedwater pump is capable of delivering a total feedwater flow of I:9003 gpm at a pressure of [11103 psig to the entrance of the steam generators..This capacity is sufficient to. ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than f3503'F when the Residual Heat Removal System may be placed into operation.

3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with steam discharge to the atmosphere concurrent with total loss-of-offsite power. The contained wate~ volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristicsirouJ <<he value hwq gbo 6ee~ Wg~i+W s~~< +~

civic.~esca~ o~ p 8 ~II ~ ~ ++ M 8474'r AW 'BhT',

3/4. 7. 1. 4 SPECIFIC ACTIVITY The limitations on Secondary Coolant System. specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of a steam line rupture. This dose also incl'udes the effects of a coincident g gpm reactor to-secondary tube leak in the steam generator of the affected steam line. These values are consistent with the assumptions used in the safety analyses.

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blow down in the event of a steam line rupture.

This restriction is required to: (1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and (2) limit the pressure" rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the Surveillance Requirements are consistent with the. assumptions used in the safety analyses.

3/4. 7. 2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure"induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of f70]'F and I:200] psig are based on a steam generator RTNDT of t.'60) F and are sufficient to prevent brittle fracture.

SHEARON HARRIS - UNIT 1 B 3/4 7-2

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CORPORATE ORGANfZATION Ll CHAIRMAN/PRESIDENT AND CHIEF EXECUTIVE OFFICER SENIOR EXECUTIVE VICE PRESIDENT SKNIOR VICE PRESIDEHT SENIOR VICK PRESIDENT MAHAOKR CORPORATE n OPERATIOHS SUPPORT HUCI.EAR QENERA'llOH QUALITY ASSURANCf 0

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ML18019A751

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