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.

Office 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 J ENCL j SIZE:

TITLE: Licensing Submittal:

PSAR/FSAR Amdts

& Related Correspondence NOTES: Application for pei mit renewel filed.

05000400 RECIPIENT ID CODE/NAME PWR-A ADTS PWR-A EICSB PWR-* PD2 LA BUCKLEY'S B 01 PWR-A RSB INTERNAL; *DM/LFMB IE FILE IE/DGAVT/GAB 21 NRR PWR-A ADTS NRR ROE'. L NRR/DHFT/MTB RQN2 EXTERNAL: 24X DMB/DSS (AMDTS)

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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 TECHNICALSPECIFICATIONS

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 willalso 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, SRZ:GAS:wc (3587GAS)

Attachments cc:

Mr. B. C. Buckley (NRC)

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

Dr. 3. Nelson Grace (NRC-RII)

Mr. Travis Payne (KUDZU)

Mr. Daniel F. Read (CHANGE/ELP)

Wake County Public Library Mr, R. A. Benedict (NRC)

S.. Z erman Manager Nuclear Licensing Section Mr. Wells Eddleman Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)

Dr. 3. H. Carpenter (ASLB)

Mr. 3. L. Kelley (ASLB)

Mr. 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

EI f ~"'i~~

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II ll

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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 LCO Number:

GENERAL Section Number:

SEE ATTACHED Comment Type:

ERROR Page 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:

a 0 A boric acid tank with:

2.

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

(0 Fy A minimum boron concentration of [7000) ppm, and b.

3.

A minimum solution temperature of

$65l F.

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 level.

Co'Po

~~~

~~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 aO b.

The above required borated water source shall be demonstrated OPERABLE:

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 when it is the source of borated water.

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:

b.

~ /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.

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~~

puJ 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 b.

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 .

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

EMERGENCY CORE COOLING SYSTEMS 3/4. 5. 4 REFUELING WATER STORAGE TANK PPillllh hr/0 Et~ilD'/ PQP7 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 is equivalent to ONE indicated level.

92.'Pe NCAA

~

k4 ~

b.

A boron concentration of i20003 ppm of~~,

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 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 .

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 Iimits 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 gal-lons of 2000 ppm borated water be maintained in the refueling water storage'3g ops 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.

The boron capability required below 200 F is sufficient to provide a SHUTDOWN MARGIN of 1000 pcm after xenon decay and cooldown from 2000F to 140'F.

This condition requires either~ 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 LCO Number:

3. Ol. 02. 0 l Section Number:

FOOTNOTE Comment:

Comment Type:

IMPROVEMENT Page Number:

3,'4 1 -7 8

9

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.

HNPP Px ooZ ance CP KI Co mxnent a Review Tec hnical Sp ecifications Recor d Number:

412 LCO Vumber:

3. 01. 02. 03 Sect ion Number:

APPLICABILITY Comment:

(:nmment Type:

IMPROVEMENT Page Number:

3i4 I-9 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 LCO Number:

3. 01. 02. 03

.Section Number:

NEW FOOTNOTE Comment Type:

IMPROVEMENT Page Vumber:

2/

k 1--9 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 LCO Number:

3. 02. 03 Section Number:

4.3.2.2 E.3 Commen t Type:

IMPROVEMENT Page Number:

3/4 Z-10 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 LCO Number:

3.03.01 Section Number:

TABLE 3.3-1 Comment Type:

ERROR Page Number:

3!4 3-3

& 4 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 LCO Number:

3.03.02 Section Number:

TABLE 3.3-3 Comment Type:

IMPROVEMENT Page Number:

3/4 3-20 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 LCO Number:

3,03.02 Section Number:

TABLE 3.3-4 Comment:

Comment Type:

ERROR Page Number:

3/4 3-31 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.

HNPP Proof and CPUT Cornme nta Review Technical S pecifica tio r~ s Record Number'."

-415 LCO Number:

',J. 03. 02 Sect ion Number:

TABLE 3. 3-4 Comment Type:

D1PROVEMEVT Page Vumber:

3/4 3-32 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 FUNCTIONAL UNIT 9.

Loss-of-Offsite Power a.

6.9 kV Emergency Bus Undervoltage Primary b.

6.9 kV Emergency Bus.'ndervoltage Secondary 10.

Engineered Safety Features Actuation System Interlocks H.A.

N.A.

H.A.

N.A.

VPn

> [48ee]

volts with a < [1.0]

second time

.delay.

44 x'9

> Dd88] volts with a WQR]

second time>'+'"

delay (withmd.

Safety Injection).

4 /2$

> [6480/ volts

'ith a

< [54.0]

second time delay (withe~+

Safety Injection).

~DRo a t

~ yqgO yolt5 haad e%<

vol ts with a ~Q seeemt time del ay%~~'"

O. IS baal IXSCcarh 49oo

> [88&&] volts with a ~g8%$ ]

second time delay withe%

Safety e

s ~

Injection)

> [CS&] volts with a < [~]

second time@0 delay (withers Safety Injection).

SENSOR TOTAL ERROR ALLONANCE TA Z

~SI TRIP SETPDINT ALLOWABLE VALUE Pack 46 'f'/8 a.

Pressurizer Pressure, P-ll H.A.

H.A.

> [2000] psig

> [1986] psig b.

C.

d.

Low-LowT, P-12 avg'eactorTrip, P-4 Steam Generator Mater Level, P-14 H.A..

H.A.

See Item 5.b above for and Allowable Values.

H.A.

> [553]'F

> [550.6]

F H.A.

H.A.,

H.A.

all Steam Generator Water Level Trip Setpoints C.

C:

CPRX Comments HNPP Proof and Review. Techaica1 Specifications Record Number:

"427 LCO Number:

3.03.02 Section Number:

TABLE 3.3-5 Comment Type:

IMPROVEMENT Page iVumber:

3/4 3-35 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.

"HNPP CPS'.L Coromenta Pr oof and Review'ec hnical S pecificatio ns Record Number':" "428 LCO Number:

3.03.02 Section Number:

TABLE 3.3-5 Comment:

Comment Type:

ERROR Page Number:

3/4 3-38 ITEM 11 -

CHANGE "ALL AUXIKLIARYFEEDHATER 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 Record Number:

"423 LCO Number:

3.03.02 Section Number:

TABLE 4.3-2 Comment:

1 Comment Type:

IMPROVEMENT Page Number:

3/4 3-40 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 LCO Number:

3.03.03.04 Section Number:

TABLE 3.3-8 Comment:

Comment Type:

IMPROVEMENT Page Number:

3/4 3-54 F

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.

CPRL Commenta HNP'Fr ooi a.ncaa Re~ie~

Te c h.nica.l Specif xcationg Re<. ord Number:

409 LCO Number:

3,03. 03. 08 Comment Type:

IMPROVEMENT 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 LCO Number:

3.03.03.08 Section Number:

TABLE 3.3-11 Comment:

Comment Type:

IMPROVEMENT Page Number:

3/4 3-67,68 46~3 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 ZONE INSTRUMENT LOCATION TOTAL NUMBER QF INSTRUMENTS ELEVATION HEAT FLAME SMOKE

~FT

~A/8 "

~A/8 *

~ll/B

1-A-4-CHLR HVAC Chiller Equipment Area 8 Cable Trays

2. 0 Reactor AuxiIia Bui 1 din Continued 261. 0 0/42 g4

.42/0 Cohf-B

,1-A-4"gLlNf cot-d'"A-4/ME COP-S 1"A-4-CQC 1-A-4-CHFA 1-A-4-CHFB Boric Acid Equipment Area 4 Corridor Cable Trays Corridor Cable Trays Corridor Cable Trays Charcoal Filter Room 1A Charcoal Filter Room 1B 261. 0 261. 0 261. 0 261. 0 261. 0 0/12 0/g 7 0/4 ~

0/5 o/e 13/0 12/0 7/0 1O/O 8/O 1-A-EPA Electrical Penetration. Area SA 261.0 O/15 15/0 1-A-EPB j-Z-s -Pv8 1-A-5-HVA

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

(-A-S-'N3 1-A-ANGRA 1"A-SMGRB 1"A-BATA 1-A-BATB 1-A-CSRA 1-g-CSRB Electrical Penetration Area SB s~imroa/

Roo> 0 A4-/8 peer HVAC Room 1A S~imraaeg ~ 8 ~~ ~> >~<

HVAC Room 1B

@weep( fiprAv $-98 f S-d8'ucT'witchgear Room A Switchgear Room 8 Battery Room IA Battery Room 18 Cable Spreading Room A Cable Spreading Room 8

261. 0 KHAN.O 286. 0 ABC. 0 286. 0 884.d 286. 0 286. 0 286. 0 286. 0 286. 0 286. 0 0/15 27 0/gi 0/15 15/0 8/o 14lo lib 15/0 J/O 18/0

~ 17/0 2/o 2/0 27g/0 15/0 1-A-ACP t"A-CSFA 12-A-6"RT1 Auxiliary Control Panel PIC Room A Terminal Cabinet Room 12"A-6-RCC1 Rod Control Cabinets Room pjpd 12-A-6-CRl" Contr ol Room ACED

~

12-A-6-APR1 AuxiIiary Relay Panels I 2.-A-&-CRl Co~vyg)g ggw PAoea.s

)g-if gv plH5 tfbmwpoA ~f 8~-4 SHEARON HARRIS - UNIT 1 3/4 3"67 286. 0 ZB,o 305. 0 305. 0 305. 0 305. 0 305.0 3'. 0 zlo 2/O 14/0

+/9 6/0 q/c.

Fca Table 3. 3-11 Continued)

PROOF A",Q,Z~,'E',V I,'OPy ZONE INSTRUMENT LOCATION TOTAL NUMBER OF INSTRUMENTS

'LEVATION HEAT FLAME SMOKE

~FT

~A/B "

~A/B)*.

(A/B)"

2. 0 Reactor Auxi1 ia 8ui1din Continued

.y 12-A-6-PICRl Process Instruments 8 Control Racks

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

-F-2-FPC 5-F-3-CHFA perer 1 Pgy~ Pfj(P j/M'5 5-F-3-CHFB Fuel Pool Cooling Pumps 8

Heat Exchangers Emergency Exhaust Charcoal Filter A Emergency Exhaust Charcoal Filter B 236.0 261.0 261. 0 O/16 o/s 0/S S/0 s/o 5-F-3-CHF-BAL Emergency Exhaust Balance 5

3 I> NK Wa&

~ALII 4.0 Diesel Generator 8uildin 261. 0 Z(y(e 0 1-0-1-OGA-RM 1.-0-1-OGB-RM 1-0-1-OGA-ASU 1"0-1"OGB-ASU

1-0-1-QQA-TK 1-0-1-OGB-TK 1-0-1"QGA-ER 1-0-1-OGB-ER 1-0-3-OGA"ES Diesel Generator 1A Diesel Generator 1B Diesel Generator Air Starting Unit 1A Diesel Generator Air Starting Unit 1B Diesel Fuel Oil Oay Tank 1A Diesel Fuel Oil Day Tank 1B Diesel Generator MCC 8 Control Panel iA Diesel Generator MCC 4 Control Panel 18 Diesel Exhaust Silencer 1A 261. 0 261. 0 261.0 261.0 2SO. 0 ZSO. 0 261. 0 261. 0 292. 0 O/10 0/10 2/0 2/0 a/z Mo-4g/0 4'/0 I

2/0 2/O 2/0

'-0-3-DGB-ES Diesel Exhaust Silencer 1B i-D-3 PdA /l8 Atilt(<wc Avdp@'oe 8 PPV8C

. 4I-g peer g+g-nag-W AccmCioa &vtn+r Roon P >PC SHEARON HARRIS -%IT 1 3/4 3-68 292.0 afz.o z9z,0 2/0 tjo

<k

g-i' b'v i~ 7-gV'Z 7-A'V PWrriPC SC ~Pi r Pu2Z

/8'-ZZA/, AE.ZZ3'8/ 0 PoRnac Z~~i'x1 S~cr gH'-Xg,~ 9/ J l 22/ 0 PoRndc.

CuPPi Yj~r A//-Eg/ gd'Q5'2P.'

2 Q

--- a)g INERT 8 L87ZR I

CoflPuWQ i gertnu4ie4 TV' PooH sic, Ju~r H-P7w,~k-g7Z Co~>uWR 4QVTRY /'VS ~izeTA'IC twnc7io~ /toes HV8C Sue~

~~-~sw y P-gG'ay.o

')~

2/0

TABLE-3. 3-13.

Continued)

PROOF AHO REV!EN 00PY ZONE INSTRUMENT LOCATION 5.0 Oiesel Oi1 Stora e Tank Area 1-0-PA Diesel Fuel Oil Pump Room 1A 242. 25 0/2 2/0 TOTAL NUMBER OF INSTRUMENTS ELEVATION HEAT FLAME

)

SMOKE

~FT

'~A/8 "

~A/8)"

(A/8)"

1-0-PB 5-0-BAL Oiesel Fuel Oil Pump Room 18 242.25 Oiesel Fuel Oil Storage Tank 242.25 Area-Balance 0/2 2/0 7/0

~

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

262. 0 mme

$0/0 12-1-ESWPB Pump Room SA Electrical Equipment Room SB Pump Room SB 262. 0 25j.7/

262. 0 262.0 2/0 F

10/0 2/0 yA&

yi4.

SHEARON HARRIS - UNIT 1 3/4 3-69

TABLE 5.3-11a

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

1.0 Rea tor Auxilia Buildin V 1-A-5-HUA EL 286 m 1-A-5-HVB EL. 286 V 12-A-6-HV7 EL. 305

~2-A-7-HV EL; 324 Svitchgear Room A AH-3.2 (1A-SA);(1B-SA) itchgear Room B

3 (lh-SB) (lB-SB)

Electzi 1 Equipment Protecti Rooms HVAC AH-16 (1A-Sh)

(1B-SB)

NNS Ventilatio AH-14 (NNS),

/

t FAD-1FP-8655-AOl FAD-1FP-8655-A02 FAD-1FP&65$'-A03 FAD-1FP&655-B01 FAD-1FP-8655-B02 FAD-1FP&655-B03 FAD-1FP-8655-B04 FAD"1FP&655-COl FAD-1FP&655W02 I

FAD-1FP-8655-D01 FAD-1FP&655-D02 FAD-IFP"8655-D03

)

FAD-1FP"S655-D04

~

~ 1-A-5-HV3 EL. 286 y'2-AW-HV7 EL. 305 (Later)

EL. 324 (Later)

EL. 324 Normal Supply S-3A (NNS) S-,3B (NNS)

.F ControX Room HVAC AH-15j(1A-SA), (1B-SB)

//

mputer 6 Communication R?f HVAC AH-97A(NNS)

AH-97B(NNS)

Computer Batr cry 6 Aux Electric Protection Rms HVAC AH-ogh r!".;<)

Ah~Nb (NNS)

FAD-1FP&655-EOl FAD-1FP&655-E02, FAD-1FP&655-E03 AD-lFP&655-E04 IFP&655-E05 F

1FP-8655-FOl FAD-FP-8655-F02 FAD-1 '6&5-F03 FAD-1F -8655-F04 FAD-1FP-8 55-601 FAD-1FP-86 5W02 FAD-1FP-8655-1 FAD-lFP&655-H 2.0 Fuel Hnndlfnj Building

~1 AW-CHFA Normal Supply (South)

.L. 261 AH-21A (NNS),

AH-2lB (hNS )

FAD-1FP-8657-AOI FAD-IF) -8057-A02 8676g

>\\

0

g 5-F-3-HV

+ EL. 261 12-A-7-HV

+ EL. 324

/ 12+-7-NV EL. 324 3.0 Diesel Generator uflding aABL,k 3, 3-I ja HVAC DUCT FIRE DETECTION INSTRU.'L~'hTS Supply Fan Smoke Detector Zone HVAC S stem Tag, No.

/

Noraal Sopp17 (North)

FBDFIFP 865-7 B01-L 68-226 (NNS>Q FDD2F-P&657 B0-2 AH-22B (NNS)'

~iFAD-1FP&657-B03 Normal Supply (Ope&tFlr)

FAD-1FP&657-C01 AN 56 -(NNS),

~

FAD iF-P 86-57 00-2 AH-57 (NNS)

Normal Supply Oper Fl)

FAD-1FP-8657-D01 AH-58 (NNS)

F~3.FP&657-D02 AH-59 (NN

~l-D-3-DGA-HVR Zly tric Equip.

EL. 292 Rm. A HVAC AHOIS, 1A-SA), AH&5 (lB-SA)

+ 1-D"3-DGB-VR Electric Equip EL. 292 Rm B HVAC AH&5 (1AWB),

AH&5 (1BWB)

FAD-1FP&658 $01 FAD-1FP&658-M FAD-1FP&658-B01 FAD-1FP-8658-B02 86768

, l gp P6(

'I )hliT g/g

. z-(n%E

0

CPRL Cornmenta HNPP Pr oof and Review Technical Specification~

Record Number:

400 LCO Num'be r:

."<. 03. 03. 11 Section Number:

TABLE 4.3-9 Comment:

Comment

'fype:

IMPROVEMENT Page Number:

3!4 3.-83 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 LCO Number:

3.05.01 Section Number:

3.5.1.b Comment Tvpe'IMPROVEMENT Page Number:

3,'4 5-1 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 LCO Number:

3.05.02 Section Number:

4.5.2.a Comment Type:

ERROH Page Number:

3/4 5-4 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 hnical S pecificatio n s Re co rd Numb e r:

'404 LCO Number:

3. 05. 02 Section Number:

Comment:

Commen t Type:

ERROR Page Number:

3/4 5-6 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 LCO Number:

3. 06. 02. 01 Sect ion Number:

4. 6. 2. 1. b Comment Type:

ERROR Page Number:

3/4 6"11 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 LCO Number:

3.06.02.01 Section Number:

4.6.2.1.c Comment:

Comment Type:

IMPROVEMENT Page Number:

3/4 6-11 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 LCO Number:

.'<.06.03 Section Number:

NEW FOOTNOTE Comment Comment Type:

IMPROVEMENT Page Number:

3/ ) 6-14 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 LCO Vumber:

3. 08. 01. 01 Section Number:

4. 8. l. l. 1. b Comment Type:

IMPROVEMEVT Page Vumber:

3/4 8-3 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 LCO 4umber:

3. 09. 12 Section Number:

ACTION A Comment Type:

ERROR Page Number:

3/4 9-14 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 LCO Number:

8 3/4. 06. 01. 0 "r Comment Type:

ERROR Page Number:

B Jj'L 6-2 Section Number:

Comment:

B 3/4. 6. l. 7 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 isolation valves dur,.ing MODES 1,

2, 3,

and It 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 LCO Number:

3. 12. 01 Section Number:

TABLE 3. 12-1 Comment Type:

IMPROVEMENT Page Number:

3/4 12-6 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 LCO Number:

R 3/4. 07. Ol. 03 Section Number:

B 3/4. 7. 1. 3 Comment:

Comment Type:

IMPROVEMENT Page Number:

B 3/4 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 pecification. s Record Number:

420 LCO iVumber:

6.02.01 8c.02 Section Number:

FIG. 6.2-1

& -2 Comment Type:

IMPROVEMENT Page Vumber:

6-3 h

4 Comment:

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

The Corporate Organization may be change) 0-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$ Lc Q t QQAP )+ ~f L~~

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 LCO Number:

6. [0. 03 Sect ion Number:

6. 10. 3. i Comment Type:

ERROR Page Number:

6-25 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.

~

Discrepancies Between FSAR and TS (3447GAS/Ijs

)

CP8c.L Cornrnenta HNPP Proof and Review Technical Specifications Record Number:"

429 LCO Number:

3.0l.02.05 5.06 Section Number:

3.1.2.5 8

.6 Commen t:

Comment Type:

FSAR/TS DISCRFPA4('3 Page Number:

3/4 1-l1 8

12 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 LCO Number:

3.05.01 Section Number:

3.5.l.c Comment Typ~:

fSAR ~TS D ISCREPANCY P'age Number:

3/4 5-l 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.

Discrepancies Between TS and SER

($447GAS/'s

)

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

Record Number:

430 LCO Number:

.".01.02.05 8

.06 Sect ion Number:

3. 1. 2. 5 h

. 6 Comment Type:

SFR/TS DISCREPANCY Page Number:

3/0

l. -1l 8

12 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.

Marked-Vp TS Pages (3447GAS/Ijs

)

REACI.Vi..'ONTROL SYSTEMS 3/4. 1. 2 BORATION SYSTEMS FLOM PATH " SHUTDOWN LIMITING CONDITION FOR OPERATION SHWPF'g 8%

PROOF ABtj REV!BY COpY 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 if the boric acid tank in Speci-fication 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

REACTIVITY CONTROL SYSTEMS CHARGING PUMP -

SHUTOOWN SHNPP

/)PI~Il

.NR

$66 I'iiuOF AHO RENB/ f,'ppy 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 equal'o 335oF/ ward the cleric,boa iressel head is i'laice.

""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 IVTT CONTROL SYSTEMS

$86 BORATED WATER SOURCE -

SHUTDOWN PP(uOF A)~0 "Zi(BY t,'gPy 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:

2.

3.

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

(0%0 A minimum boron concentration of [7000] ppm, and T

, 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, which is equi val ent to ~Vindicated 1 eve 1 (P90 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 b.

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 when it is the source of borated water.

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 1-11

REACTIVITY CONTROL SYSTEMS

'ORATED WATER SOURCES " OPERATING LIMITING CONDITION FOR OPERATION MAR

$86 c

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:

2.

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

'f0'lo

'A minimum boron concentration of [7000] ppm, and b.

3.

A minimum solution temperature of [65)

F.'he refueling water storage tank (RWST) with:

y3(ohio 1.

A minimum contained borated water volume, of [~88&3 gallons, which is equivalent to ~S indicated level.

qgqo t gives~

~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 b.

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 .

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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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

POWER DISTRIBUTION LIMITS SHi P>

P~y~

er ~

~

MN 88o PROOF AND REVIEN COPY 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

'emonstrated, through incore flux mapping and RCS total flow rate comparison, to be within acceptable limits to exceeding the following THERMAL POWER levels:

l.

2.

3o A nominal 50K of RATED THERMAL POWER, A nominal 75K of RATED THERMAL POWER, and 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 at least once per 18 months.

SHEARON HARRIS " UNIT 1

'/4 2-10

FUNCTIONAL UNIT TABLE 3. 3-1 Continued REACTOR TRIP SYSTEM INSTRUHENTATION HINIHUH TOTAL NO.

CHANNELS CHANNELS OF CHANNELS

'IO TRIP OPERABLE APPLICABLE MODES ACTION 12.

Reactor Coolant FlowLow a.

Single 'Loop (Abpve P-8) b.

Two Loops (Above P-7 and below P-8) 13.

Steam Generator Mater Level--Low-Low 3/loop 3/loop.

3/stm.

gen.

2/loop in any oper-ating loop 2/loop in two oper-ating loops 2/stm.

gen.

in any oper-ating stm.

gen.

2/loop in each oper-ating loop 2/loop 1

each oper-ating loop 3/stm.

gen.

1, 2 each oper-ating stm.

gen.

645m(l) 14.

Steam Generator Mater LevelLow Coincident Mith Steam/

'eedwater Flow Hismatch 2 stm.. gen.

level and 2 stm./feed-water flow mismatch in each stm.

gen.

1 stm.

gen.

level coin-

~

cident with 1 stm./feed-water flow mismatch in same stm.

gen.

1 stm.

gen.

level and 2 stm-/feed-water flow mismatch in same stm.

gen.

or 2 stm.

gen.

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

gen.

1. 2 15.

Undervoltage Reactor Coolant PUmps (jgbygg, p~7 2/pu p R/Pea>N 2 pe,ANT 1

68(1)

TABLE 3. 3-1 Continued REACTOR TRIP SYSTEH INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.

OF CHANNELS CHANNELS TO TRIP MINIHUH CHANNELS OPERABLE APPLICABLE HODES ACTION 16.

Underfrequency Reactor Coolant Pumps (Above 'P-7) 17.

Turbine Trip a.

Low Fluid Oil Pressure b.

Turbine Throttle Valve Closure 18.

Safety Injection Input from ESF 3

4 2/qTIAi~

2I 1, 2 68 108 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 e.

Turbine Impulse Chamber

Pressure, P-13 1

2

TABLE 3. 3-3 Continued ENGIHEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TOTAL HO.

CHANNELS OF CHANNELS TO TRIP I

g

'UNCTIONAL UHIT 3.

Containment Isolation (Continued)

MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION M

2)

Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4

. 14 40 I

Cl 3)

Containment Pressure High-3 c.

Containment Ventilation Isolation 1)

Manual Containment

'pray Initiation See Item 2.c.

above for Containment Pressure High-3 initiating functions and requirements.

See Item 2,a.

above for Manual Containment Spray initiating functions and requirements.

y.9~

2)

Automatic Actuation Logic and Actuation Relays

.2 1, 2, 3, 4, 6*4'7, 25 3)

Safety Injection 4)

Containment Radio" activityHigh 5)

Manual Phase "A"

Isolation See Item l..above for all Safety Injection initiating functions and requirements.

CL P~, tNIWW SSOhkaanr Sigma A<~

See Table 3.3-6, Item lr for Containment Radloectlofty~igh initiating functions and requirements See Item 3.a.l) above for Manual Phase "A" Isolation initiating unctions and requirements.

PIERCC ua d6'at

"<Chai 4m.

Akmea~elS

~>~c{cpf +les ~of< so 4 +,~s ~~ "cL~Aids W+~iP" ~]~

RQ

TABLE 3.3-4 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT M

EIT 6.

Adxiliary Feedwater (Continued) g.

Steam Line Differential Pressure High 5.0 1.47 3.0

< '100psi

< 127.4 psi I

SENSOR TOTAL ERROR ALLONANCE TA Z

~S TRIP SETPOINT ALLOUABLE VALUE Coincident With:

Main Steam Line Isolation 7.

Safety Injection Switchover to

. Containment Sump a.

Automatic Actuation Logic and Actuation Relays N.A.

N.A.

See Item 4.

above for Main Steam Line Isolation Trip Setpoints and Allowable Values.

y TIOO o

)

g 'll CA b.

RMST LevelLow-Low

'.A.

N.A.

23.'f

> [08e43X Coincident With Safety Injection See Item l. above for all Safety Injection Trip Setpoints and Allowable Values.

8.

Containment Spray Switchover to Containment Sump a.

. Automatic Actuation Logic

'nd Actuation Relays N.A.

N.A.

b.

RMST"-Low-Low Coincident Mith:

Containment Spray See Item 7.b.

above for all RMST Low-Low Trip Setpoints and Al1 owabl e Values.

See Item 2.

above for all Containment Spray Trip Setpoints and Allowable Values.

9R

TABLE 3.3-4 Continued ENGINEERED SAFETY FEATURES ACTUATIOH SYSTEM IHSTRUMENTATIOH TRIP SETPOINTS Ti Q)

~X

'J$ K

) 0 0

FUNCTIONAL UNIT 9.

Loss-of-Offsite Power s

a ~

6.9 kV Emergency Bus Undervoltage Primary

- b.

6.9 kV Emergency Bus.'ndervoltage Secondary 10.

Enginee'red Safety Features Actpation System Interlocks N.A.

N.A.

TOTAL ALLOWANCE TA Z

N.A.

9gfn

> [4048]

volts with a < fl.0]

second time

,delay.

Otal 2'f

.> [&S&) volts with a

/ED second time>'~

delay (with~

Safety Injection).

6'IZV

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

second time delay (withdI~+

Safety Injection).

SENSOR ERROR

~S)

TRIP SETPOIIIT ALLOWABLE VALUL T~)Ro a

~ rrs$fO aTOI<5 Pi~4 gpss

>,.f4993 volts with a ~%&3 f time del aybc~'"

EI,Q $s-pIosd IXSCcoodS rtsgoo

> [408k] volts with a <~$

)

see~f time delay with+et Safet~ '~<<

IVhsscf PO'<Co~d S Injection).

4,VW

> [489&] volts with a < [~)

second time delay (without Safety Injection).

z g7g a.

Pressurizer Pressure, P-ll N.A.

H.A.

> [2000] psig

> [19e6] pslg b.

C.

Low-LowT, P-12 avg'eactorTrip, P-4 N.A.

H.A.

N.A.

H. A.

N.A.

> [553] F

> [550.6]'F Steam Gener ator Water Level, P-14 See Item 5.b above for all Steam Generator Water Level Trip SetpoiIIts and Allowable Values.

RFVISION NR SSS TABLE 3.3-5 Continued l'Itoof QP LBlN LOB'NGINEERED SAFETY FEATURES

RESPONSE

TIMES INITIATINGSIGNAL AND FUNCTION 3.

Pressurizer Pressure Low (Continued) a.

Safety Injection (ECCS) (Continued) 5)

Auxiliary Feedwater Motor Driven Pumps 6)

Emergency Service Hater Pumps 7)

Containment Fan Coolers 8)

Control Room Isolation 4.

Hain Steam Line Pressure Low "

a.

Safety Infection (ECCS) 1)

Reactor Trip 2)

Feedwater Isolation 3)

Containment Phase "A" Isolation 4)

Containment Ventilation Isolation 5)

Auxilfary Feedwater Motor Op'fven Pumps 6)

Emergency Service Mater Pumps 7)

Containment Fan Coolers 8)

Control Room Isolation b.

Steam Line Isolation 5.

Containment Pressure<<-High-3 a.

Containment Spray b.

Phase "B" Isolation 6.

Containment Pressure High-2 Steam Line Isolation g~~vc 7.

~ Steam Line Pressure - QeyeAe RateHigh

~

Steam Line Isolation

RESPONSE

TIME IN SECONOS

< [60]

F

< t:32](')/t:22]( '

$27](1)/t:17]<)

N.A.

< I:12]

/(22]

< t2]

< p7](3) t~(2)/t~j(1)

(6)

< f60]

t F

$32](+)/f22](~)

< p7](1)/$17](g rF.S

< [4e4er j(+)/[32.2j

$22.5]( )/t:12]

<<7]~

< pj~

SHEARON HARRIS - UNIT 1 3/4 3-35

SHNPP RpVic;Inc

~

gg 586 TABLE 3.3-5.

Continued ENGINEERED SAFETY FEATURES

RESPONSE

TIMES PAQQF Afl3 IiBlB COPY INITIATINGSIGNAL ANO FUNCTION 8.

Steam Generator Mater Level""High-High a.

Turbine Trip b.

Feedwater Isolation 9.

Steam Generator Mater LevelLow-Low a.

Motor-Driven Auxiliary Feedwater Pumps b.

Tur bine-Driven Auxi1iary Feedwater Pump 10.

Loss-of-Offsite Power w~~ ~~~ Turbine-Driven Auxiliary Feedwater Pump Trip of All Main Feedwater Pumps

~~g.

DRLvc&

~ Auxiliary Feedwater Pumps Steam Line Differential Pressure-High

~ Coincident with Main Steam Line Isolation Signal Isolate Auxiliary Feedwater to the Affected Steam Generator 13.

RWST LevelLow-Low

RESPONSE

TIME IN SECONDS

< [2.5$

<7~(3)

< E603

< f603

< f60)

N.A.

I:N.A. g a ~

b.

Safety Injection Switchover to Containment Sump Coincident with Safety Injection

~

Safety Injection Switchover to Containment Sump Coincident With

'ontainment Spray

< [323

< 51033 14..

ddi ii ili 4sohaUaa a-. CDWm~~c~f P~n)e Xsota+r~

5](6>7)

SHEARON HARRIS - UNIT 1 3/4 3-36

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM IHSTRUHENTATIOH SURVEILLANCE RE UIREMENTS CHANNEL FUNCTIONAL UNIT ANALOG CHANNEL CHANNEL

CHANNEL, OPERATIONAL CHECK CALIBRATION TEST TRIP ACTUATING MODES DEVICE MASTER SLAVE FOR MHICH OPERATIOHAL ACTUATION RELAY

"; RELAY SURVEILLAHCl TEST LMI TEH TE T

. YE Y REtE

3. Containment Isolation (Continued)

3) Containment S

Pressure High-3 N.A.

H.A.

N.A.

1, 2, 3

H.A.

c. Containment Ventilation

~

~c, Isolation

1) Manual Containment See Item 2.a.

above for Manual Containment'Spray Surveillance Requirements.

'Q c Spray Initiation "P5

2) Automatic Actuation 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~~ Surveillance Requirements Radi oacti vityHigh A

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

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.

b. Automatic Actuation H.A.

Logic and Actuation Relays

c. Containment Pressure S High-2 H.A.

N.A.

H.A N.A.

N.A.

-H.A.

M(1)

N.A.

1,2, 3

N.A.

1, 2, 3

M(1) q 1,2, 3

RR/tc;la~i TABLE 3. 3-8 P800F AHO EISlBI MPY INSTRUMENT 1.

Wind Speed 2.

Wind Oirection METEOROLOGICAL MONITORING INSTRUMENTATION LOCATION Nominal Elev. 12.5 meters Nominal Elev. 61.4 meters Nominal Elev. 12.5 meters Nominal Elev. 61.4 meters MINIMUM OPERABLE 3.

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

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION SHNPP-PP

$(f~%) ~ a

~

MAR 3986 PROOF A'$D RPtIEI Capy 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:

b.

C.

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).

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).

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

'ccessible during plant operation shall be demonstrated OPERABLE at least once 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.

H

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

<e~ ~,4 he ueei4leJ. ~ f'"

4o< S~oke 'defeefons shoa l t be.

vel'if~ed oa

<@cay de.eR Pasd va/.

SHEARON HARRIS - UNIT 1 3/4 3-65

8 Hi" P P RPJjSjQt

~

NR 11m TABLE 3. 3-11 ConAKRd FIRE OETECTION INSTRUMENTATION PROOF AND PB)P(V COPY 1-A-4"CHLR Coh-8 1-A-4-PlNf cow@

1-A-4/ME Cdd-I 1"A-4-CQC HVAC Chiller Equipment Area 8 Cable Trays Boric Acid Equipment Area 4 Corridor Cable Trays Corridor Cable Trays Corridor Cable Trays ZONE INSTRUMENT LOCATION

2. 0 Reactor Auxi 1 ia Buildin Continued 261. 0 0/.4d g4.

.42/0 261. 0 0/12 13/0 261. 0 261. 0 0/g 0/4' 12/0 7/0 TOTAL NUMBER OF INSTRUMENTS ELEVATION HEAT FLAME SMOKE

~FT

~A/B *

~A/B

1-A-4-CHFA Charcoal filter Room 1A 1-A-4-CHFB Charcoal Filter Room 1B 261. 0 261. 0 0/5 o/4 10/0 8/0 1-A"EPA Electrical Penetration Area SA 261. 0

-O/15 15/0 1-A-EPB

/-1-S -P'V8 1-A-5-HVA

/-g -g-kva 1-A-5-HVB

/-A-s'-N8 1-A-MRA Electrical Penetration Area SB S~~~eae~

Resow 4 W-/P.

DuCr HVAC Room 1A Satimraaeg ~ 3 A///> >~<

HVAC Room 1B ALee~c Sw~v 5-9A j HE suer Switchgear Room A 261. 0 zBC.O 286. 0 2'Bd, o 286. 0 884.d 286. 0 0/15 15/0 8/o 14/o P/o 15/0 w/o 18/0 1-A-MRB Switchgear Room B

286. 0 17/0 1"A-BATA 1-A-BATH 1-A-CSRA 1-Jf-CSRB Battery Room 1A Battery Room 1B Cable Spreading Room A Cable Spreading Room 8

286. 0 286. 0 286. 0 286. 0 27 0/g 0/15 2/0 2/0 27 pX/0 15/0 1-A-ACP Auxiliary Control Panel t-Cl-C~RA P~C %em A 12-A-6-RT1 Terminal Cabinet Room

'2-A-6-RCC1 Rod Control Cabinets Room gplhl 12-A-6-CR1 Control Room Adea 12-A-6-APRl Auxi1iary Relay Panel s jz-A-&-col Co~~< go~

PA~ecs

)g-8 gV pfyS Vavn<y~d Acr 0-P/

SHEARON HARRIS - UNIT 1 3/4 3-67 286. 0 ZB.o 305. 0 305. 0 305. 0 305. 0 305.o 3'. 0 2/0 2/O 14/O

<g/0

~ +/0 6/0 9/o

!/g

'SHNPp 8 -V$Sit. '.I Tab 1 e 3. 3-11 Continued',

PROOF Ai"0 PE;.~"E>'l t',O'Y INSTRUMENT LOCATION TOTAL NUMBER OF INSTRUMENTS ELEVATION HEAT F LAME SMOKE

~FT

~A/8 * ~A/8)"

(A/8)"

2. 0 Reactor Auxi 1 ia Bui 1 din Continued g 12-A-6-PICR1 Process Instruments

& Control

,ja

(

Racks c

l? R j/1) 0 coHTjpoc Ann Pgifc AA'/Z Qcr

)y ~)

gC 12-A-6-HV7 HVAC Eauipment Room

//y7 ccEcrAltgc. aquiAesvr fm7PeTlod 305. 0 Zcu. 0 305. 0 0/4'8 s/o e/o zyg/0 z/o z/o "F-2-FPC 5-F-3-CHFA pv'zer 1

/N<

5-F-3-CHFB Fuel Pool Cooling Pumps Heat Exchangers

. Emergency Exhaust Charcoal Filter A

Emergency Exhaust Charcoal Filter B 236. 0 261. 0 t

Z61. 0 O/16 o/8 0/8 8/0 8/0 5-F-3-CHF-BAL Emergency Exhaust Bal ance 5

.'S.l<<"IZ elar

<<<<<<<<A<<

4.0 Diesel Generator Buildin Z61. 0 Z&J ~ 0

<<<<<<4/0 iZ./n 1-0-1-OGA-RM 1-0-1-OGB-RM 1-0"1-OGA-ASU'-0-1-DGB-ASU

. 1-0-1-DGA-TK 1-0-1-OGB-TK 1.-0-1-QGA-ER 1-0-1-QGB-ER Diesel Generator 1A Diesel Generator 1B Diesel Generator Air Starting Unit 1A Diesel Generator Air Starting Unit 1B Diesel Fuel oil Oay Tank lA Diesel Fuel Oil Day Tank 1B Diesel Generator MCC & Control Panel 1A Diesel Generator MCC & Control Panel 1B

'61.0 261. 0 261.0 261. 0 280. 0 280. 0 261. 0 261.0 o/1o p/0 4

O/1O 4;8/0 2/o 2/0 2/0 2/0 1-0-3-OGA-ES Diesel Exhaust Silencer 1A 1-0-3-QGB" ES Diesel Exhaust Silencer 1B i"b-3.pAO.Ã4 Zi.tutrix A~Nnoe'on R /INC

. Q-g Ncv'+4-NS.N Ekgc7ltiofa EwrnQr Peen P PIC SHEARON HARRIS -%IT 1 3/4 3-68 292. 0 292. 0 292,O z9z. 0 vv 2/0 2/0 ajo

<//o

pogrig@

Sv~Pc r Puc~

Ah'-ZZA,'H'~25 24/ 0 Porqn~c Saucy 5'vcr gjf-fgf gP'XP'25. ~

Awnac.

GPPc y 5~r Ag'Xgfgd'Qj'ZP'.0 I

Coedu~g j'onnuNic'pl77i4 4 kioA Pgc, /~der 4P-1r"A,ek'-)7Z zan o lo I

Con/vaR I+77ZgYf AVE Hno&IC'u~

c Tio 80~S HV8C 2>c->

f Hp -/ST dan. 4 2 Q

t JiSIQN TABLE 3.3-11 Continued}

PBDOF AjIO IIEVIESY COPY

<NR

. $86 ZONE INSTRUMENT LOCATION TOTAL NUMBER OF INSTRUMENTS ELEVATION HEAT FLAME SMOKE FT

'~A/8 *

~A/8 *

(A/8)"

5.0 Oiesel Oil Storm e Tank Area I"0-PA Diesel Fuel Oil Pump Room IA 1-0"PB 5"0-BAL Oiesel Fuel Oil Pump Room 18 Oiesel Fuel Oil Storage Tank AreaBalance 6.0 Emer enc Service Water Intake Structure 12"1-ESWPA Electrical Equipment Room SA 242.25 242.25

. 242. 25 251. 7/

262. 0 0/2 0/2 2/0 2/0 7/0 m<<w 9'0/0 12-1-ESWPB Pump Room SA Electrical Equipment Room SB Pump Room SB 262. 0 25I. 7/

262. 0 262.0-2/0 10/0 2/0 yP,('g

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

TABLE 9.3"Ila r

HVAC DUCT FIRE DETECTION INSWUHWTS

':,ii f',!.P ]"

(,'"~ f ') >> )~ a a

i'I I) l Sup y Fan Zone HVAC S stem 1.0 Rea tor huxilia Buildin Smoke Detector Tag No.

V 1-A-5-HVA EL. 286 v 1-A-5-HVB EL. 286 V 12-A-6-HV7 EL. 305 S~itchgear Room A AH-12 (1A-SA),,(1B-SA) itchgear Room B

3 (lA-SB) (1B'-SB)

Electri 1 Equipment Pz'otecti Rooma HVAC AH-16 (IA-SA)

'1B-SB)

I FAD-1FP-8655-A01 FAD-1FP-8655-A02 FAD-1FP&65$-A03 FAD-1FP&655-BOl FAD-lFP-8655-B02 FAD-1FP&655-B03 FAD-1FP-8655-B04 FAD-IFP&655-C01 FAD-1FP&655M02 SHg pp REVtsfON MAR

~986

~2-A-7-HV EL. 324 NNS Ventilatio AH-14 (NNS)

FAD-1FP-8655-DOl j'AD-1FP-8655-D02 FAD-1FP-8655-D03 FAD-1FP-8655-D04!

1-A-5-HV3 EL 286 y'2-AW-HV7 EL. 305 (Later)

EL. 324 (Later)

EL. 324

/

Norma1 Supply s-3A (NNs) s-,3B (NNs)

I ControX Room HVAC AH-aSj(1A-SA), (1B-SB) mputer 6 Communication RH HVAC AH-97h(NNS)

AH-97B(NNS)

Computer Battery 6 Aux Electric Protection Rma HVAC hH-98A ')".'&),

hi)-. 'ih ( NNS )

FAD-1FP&655-EOl FAD-lFP&655-E02, FAD-1PP&655-E03 AD-1FP&655-E04 1FP&655-E05 F

1FP-8655-F01 FAD-FP-8655-F02

-ee>5-Fu3 FAD-aF 8655-FO4 FAD"1FP-8 55-G01 FAD-lFP-86 5W02 FAD-1FP-8655-1 FAD-lFP&655-H 2.0 Fuel Handling Building V 1 AW-CHFA Normal Supply (South)

-L. 261

'H-21h (NNS},

AH-21B (hNS )

FAD-1FP-8 657-AOI k'ILD-Ik )'-ebb 7-A02 86768

~l

5-F-3-HV

+ EL. 261 12-A-7-HV

+ EL. 324

/12%-7-HV ZL. 324 Normal Suppl AH-58 (NNS)

AH-59 (NN 3.0 Diesel Generator uildi iABLE 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)

Noanal Sup 7 (Norah)

FABFIFP 86-57 80-1 L

AH-22A (NNS),

FADa-1FP&657-B02 AH-22B (NNS)'

yFAD-1FP&657-B03 Normal Supply (Oper'Fl'K FAD-IFP&657-C01 AH-56 (NNS),

~

FAB-1FP-8657-002 AH-57 (NNS)

Oper Fl)

FAD-IFP-8657-D01 F~FP&657-D02

~l-D-3-DCA-HVR Ely tric Equip.

EL. 292 Rm. A HVAC AH&58.

lA-SA), AH&5 (1B-SA) 1-D-3-DGB-VR Electric Equip EI 292 Rm B HVAC AH&5,(1AWB),

AH&5 (1BWB)

FAD-IFP-8658 boa FAD-1FP&658-~

FAD-1FP&658-B01 FAD-1FP-8658-B02 8676g Qp piC I 4'IBT g/4. (r>E

m Sa CD INSTRUMENT TABLE 4.3-9 Continued RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS

])(gzrA.

CHANNEL MODES FOR NlICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE CIIECK CIIECK CAKIER EIRE TE I IC REISIRED tab 5.

WASTE PROCESSING BUILDING VENT STACK 5 a.f.

Noble Gas ActivityHonitor(<<C)

D gable Cae Ac4<e<ty W+<<<<~ot (QR4%) >

b.

Iodine Sampler M

c.

Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Monitor MASTE PROCESSING BUILDING VENT STACK 5A N.A.

N.A.

R(3)

N.A.

N.A.-

qN a.

Noble Gas Activity Honitor b.

Iodine Sampler c;

Particulate Sampler d., Flow Rate Monitor ~

-e.

Sampler Flow Rate Monitor

~ aA.

~u,A.

N;A.

N.A.

N.A.'.A.

R(3)

N.A.

rn

3/4."

":MERGENC.

"ORE COOLING S

S EMS 3/4.5. 1 ACCUMULATORS COLO LEG INJECTION LIMITING CONDITION FOR OPERATION RF..Vi3iQI'j PRDQF AND RPttP(Y COPY 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

EMERGENCY CORF COOLING SYSTEMS 3 H Ni P P Pt":g )~3-'~t'I MAR

$986 PROOF APJO AEVIEY/ COPY SURVEILLANCE RE UIREMENTS Continued)

CP8(L Valve No.

f]k'SI-107 X/Si-S6 ipse-52 fgSI-340 ggSI-341 XII"359 b.

C.

EBASCO Valve 8o.

Valve Function 2SI"V500SA-1 High Head Safety Injection to Reactor Coolant System Hot Legs Valve Position" Closed"1 2SI-V501SB-1 High Head Safety Injection to Reactor Coolant -System Hot Legs ZSI-V502SA-1 High Head Safety Injection to Closed-1 Reactor Coolant System Cold Legs 2SI-V579SA-1 Low Head Safety Injection to Open"1 Reactor Coolant System Cold Legs 2SI"V578SB-1 Low Head Safety Injection to Open-1 Reactor Cool'ant System Cold Legs 2SI-V587SA-1 Low Head Safety Injection to Reactor Coolant System Hot Legs Closed"1 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.

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-1The 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

EMERGENCY CORE COOLING SYSTEMS PAOQF Ai,'0 narlBv c;;Y SURVEILLANCE RE UIREMENTS Continued

>ivV V

HPSI SYSTEM EBASCO Valve No.(FSAR) 25 I-V16SA-1 2SI-V22SB-1 2S I-V28SA-1 2SI-V62SA-1 25 I-V68SB-1

~

2S I-V74SA-1 2SI-V38SA"1 2S I-V44S8-1 2SI-V50SA-1 2SI-V83SA-1 2SI-V89S8-1 2S I-V95SA-1 HPSI SYSTEM

.EBASCO Valve No.

2SI-V440SA-1 2SI-V439SB-1 2SI-AS6& +gap sh-l 2SI-V437SA-1 2SI-V436SB-1 25 I-V435SA-1 2SI"V434SA-1 2SI "V433SB-1 2SI-V432SA-1 2SI-V431SA-1 2SI-V430SB"1

, 2SI-V429SA-1 HPSI SYSTEM CPCL Valve No.

XZSI-5 5 XSI-6 XII-7 ggSI-69 ggSI-70 g gSI-71 SXSI-101 8 lSI-102 SlSI-103 ggSI" 124 4 gSI-125 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

EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE TANK 8 H i>~ ~" P ptq p]~

PROOF AHO Rt~ilEN COPY 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 is equivalent to 40'ndicated level.

qgyy

~~

~

Pud

~

Pi b.

A eierieee boron concentration of [2000] ppm ~~~,

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

CONTAINMENT SYSTEMS SHgpp

>FVrSy <<

MAR j986 PHQOF AtJO REVIEW COPY 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

'lso to Specification 3.6.2.3 Action.

SURVEILLANCE RE UIREMENTS 4.6.2.1 a.

b.

C.

d.

Each Containment Spray System shall be demonstrated OPERABLE:

'i 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; By verifying, that on recirculation flow, each pump develops a

discharge pressure of greater than or equal to~ psig when tested pursuant to Specification 4.0.5; Zf8 At least once per 18 months during shutdown, by:

Verifying that each automatic valve in the flow path actuates to its correct position on"containment spray actuation ~

test signal and 2.

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

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

CONTAINMENT SYSTEMS 3/4. 6. 3 CONTAINMENT ISOLATION VALVES BH(<J pp PF~j <, ~~< ~ ~

MAR

]985 PFQQF hiJ9 flBiBi~0py LIMITING CONDITION FOR OPERATION

.LETh i

i 1

I ifidi ~h11 OPERABLE with isolation times as shown in 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 d.

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 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+ 'PRofeA

.6.3.1 Th t

1 i

1 p if' 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.

z~eA.c'1 6y 9, 7. I 5

+gate pf'A5I O'S SHEARQN HARRIS - UNIT 1'/4 6-14

ELECTRICAL POWER SYSTBlS A.C.

SOURCES OPERATING LIMITING CONDITION FOR OPERATION PROOF IID REVIEN COPY HNPP tsar v QR

$86 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:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignment and 8

88818111 1

8 18 8 ~dy 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&7P5tf 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.

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

REFUELING OPERATIQ4S 3/4.9.12 FUEL HANDLING BUILDING EMERGENCY EXHAUST LIMITING CONDITION FOR OPERATION PROOF AIjO HE'AYA'OPY R~tc,inn,i MAR I86 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:

b.

Ce 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 of'eing powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of HEPA filters aod charcoaI adeorber/

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.

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 is

$6600) cfm t 10%

SHEARON HARRIS - UNIT 1 3/4 9-14

TABLE 3.12-1 Continued SAMPLIHG AHD COLLECTION FRE UEHCY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM HUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AHD AHD/OR SAMPLE SAMPLE LOCATIONS(

Il 4.

Ingestion (Continued)

TYPE AHD FRE(UEN( )

OF ANALYSIS b.

Fish and Inverte-br ates c.

Food Products S,u~Ash One sample of~ey84s-,

Cat-fish, and Large-Mouth Bass species in vicinity of plant discharge area.

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

Samples pf three different kinds of broad leaf vegeta-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 similar broad leaf vegeta-tion grown 15 to 30 km dis-tant in the least prevalent wind direction if milk sam-pling is not performed.

Sample in season, or semiannually if they are not seasonal.

Monthly during growing'season.

Monthly dur ing growing season.

Gamma isotopic analysis on edible portions.

Gamma isotopic and I-131 (4) analyst s.

Gamma isotopic and I-131 analysis.

Rex N+

I o

REACTIVITY CONTROL SYSTEMS QP~)~~P PROOF AHO 8>'tEN 0CJ P 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.

The boron capability required below 200 F is sufficient to provide a

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

This condition requires either~ gallons of t:7000] ppm borated water be maintained in the boric acid storage/tanks or t.~4%&) gallons of 2000 ppm borated water be maintained in 'the RWST.

/

72,oat SHEARON HARRIS - UNIT 1 B 3/4 1-2

CONTAINMENT SYSTEMS BASES SHWF P A~lc,inc,i NR 586 PROOF A80 HKVfB'k COPY 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 AUXILIARYFEEDMATER 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

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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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ML18019A751

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