ML18009A733

Forwards Retyped Tech Spec Pages,Per 900910 Application for Amend to License NPF-63 Re RCS pressure-temp Limits

ML18009A733
Person / Time
Site:	Harris
Issue date:	11/20/1990
From:	Loflin L CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLS-90-242, NUDOCS 9011290165
Download: ML18009A733 (12)

Text

ACCELERATED DIST BUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)

ACCESSION NBR:9011290165 DOC.DATE: 90/11/20 NOTARIZED:

NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION LOFLIN,L.I.

Carolina Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

DOCKET 05000400

SUBJECT:

Forwards retyped Tech Spec pages,per 900910 application for "amend to License NPF-63 re RCS pressure-temp limits.

DISTRIBUTION CODE:

AOOID COPIES RECEIVED:LTR I

ENCL J SIZE:

TITLE: OR Submittal:

General Distribution l.

NOTES:Application for permit renewal filed.

D S

05000400

/

RECXPXENT ID CODE/NAME PD2-1 LA BECKER,D INTERNAL: ACRS NRR/DET/ESGB NRR/DST SE2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: NRC PDR COPXES LTTR ENCL 1

1 2

2 6

6 1

1 1

1 1

1 1

1 1

0 1

1 1

1 RECIPIENT XD CODE/NAME PD2-1 PD NRR/DET/ECMB 9H NRR/DOEA/OTS B1 1 NRR/DST/SELB SD NRR/DST/SRXB SE OC/LFFILE 01 NSIC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

0 1

1 1

1 D

D D

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 24 ENCL 4 22 D

D

ggQ[l, Carolina Power & Light Company NOV 2 O)9SO SERIAL:

NLS-90-242 10CFR50.

United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 RETYPED TECHNICAL SPECIFICATION PAGES REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITS Gentlemen:

On September 10, 1990, Carolina Power 6 Light Company requested a License Amendment for the Shearon Harris Nuclear Power Plant, Unit 1, Technical Specifications concerning the Reactor Coolant System Pressure-Temperature Limits.

This change revises the heatup and cooldown limitations of Specification 3/4.4.9.

Enclosure 1 provides the retype'd, amendment bar pages for your convenience in issuance of the proposed Technical Specification change.

Please refer any questions regarding this submittal to Mr. Steve Chaplin at (919) 546-6623.

Yours very truly, yap Leonard I. Loflin

$o c-Manager Nuclear Licensing Section LIL/lmr (rtspage)

Enclosure cc:

Mr. R. A. Becker Mr. D. H. Brown Mr. S.

D. Ebneter Mr. J.

E. Tedrow

,r

.j 9011290165 901120 PDR ADOCK 05000400 F'DC g )

411 Fayettevilte Street o P. O. Box 1551 o Raleigh. N. C. 27602

,o(

i I

, I l

ENCLOSURE 1

SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 RETYPED TECHNICAL SPECIFICATION PAGES REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITS

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE FIGURE 3.4-4 MAXIMUM ALLOWED PORV SETPOINT FOR THE LOW TEMPERAT OVERPRESSURE SYSTEM...................................

URE 3/4.4.10 STRUCTURAL INTEGRITY......................................

3/4.4.11 REACTOR COOLANT SYSTEM VENTS.........................

~

~

~ ~ ~

3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.4.9 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System....................................

FIGURE 3.4-2 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS-APPLICABLE UP TO 5

EFPY.

~ ~. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~

~

~ ~ ~

FIGURE 3.4-3 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS-APPLICABLE UP TO 5 EFPY...................................

TABLE 4.4-5 DELETED...............................................

TABLE 4.4"6 MAXIMUM COOLDOWN AND HEATUP RATES FOR MODES 4, 5

AND 6 (WITH REACTOR VESSEL HEAD ON) ~

~ ~

~ ~

~

~

~

~

~

~ ~ ~

~

~

~

~

~

~

~

~

~

~

Pressurizer.........................,...,,................

Overpressure Protection Systems...........................

3/4 4-33 3/4 4-35 I

3/4 4-36 3/4 4-37 3/4 4-38 3/4 4-39 3/4 4-40 3/4 4-41 3/4 4-43 3/4 4-44 3/4.5.1 3/4.5.2 3/4.5.3 3/4.5.4 ACCUMULATORS ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~

ECCS SUBSYSTEMS - T GREATER THAN OR EQUAL TO 350'F.

ECCS SUBSYSTEMS - T LESS THAN 350'F

~

~

~ ~

~ ~ ~ ~

~

~

~

~

~

~

~

~

REFUELING WATER STORAGE TANK..........................

3/4 5-1 3/4 5-3 3/4 5-7 3/4 5-9 SHEARON HARRIS UNIT 1

V1 11 Amendment No.

REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS APPLICABLE UP TO 5 EFPY 2800 2600 MATERIAL PROPERTY'ASES:

Controlling Material Copper Content Nickel Content Regulatory Guide RT NpT Initial RTNDT at 1/4 T RTNpT at 3/4 T Instrument Error Applied Plate B4197-2 0.1 0%

0.50%

1.99, Rev.

2 86'F 175'F 159'F

=+10'F and -60 psig 2400 2200 2000 1800 cy 5/

'R 10 HR 50'/HR 1600 1400 1200 LLJ I

1000 o

Z:

800 600 20/ HR 400 200 100 140 180 220 260 300 340 380 420 INDICATED TEMPERATURE DEGREES F

FIGURE 3A-2 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS APPLICABLE UP TO 5 EFPY SHEARON HARRIS UNIT 1

3/4 4-35 Amendment No.

REACTOR COOLANT SYSTEM HEATUP LIMITATIONS APPLICABLE UP TO 5 EFPY 2800 2600 MATERIAL PROPERTY BASES:

Controlling Material Copper Content Nickel Content Regulatory Guide RTNpT Initial RTNpT at 1/4 T RTNpT at 3/4 T Instrument Error Applied Plate B4197-2 0.10%

0.50%

1.99, Rev.

2 86'F 175'F 159'F

=+10'F and -60 psig O

0 100'/HR 2400 2200 2000 1800 50'R 1600 I

1400 1200 IJJI 1000 o

Oz 800 30'R 600 1O/HR 2O'/HR 400 200 100 140 180 220 260 300 340 380 420 INDICATED TEMPERATURE DEGREES F

FIGURE 3.4-3 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS APPLICABLE UP TO 5 EFPY SHEARON HARRIS UNIT 1

3/4 4-36 Amendment No.

TABLE 4.4-6 MAXIMUM COOLDOWN AND HEATUP RATES FOR MODES 4

5 AND 6 (WITH REACTOR VESSEL HEAD ON)

COOLDOWN RATES TEMPERATURE""

COOLDOWN IN ANY 1

HOUR PERIOD'"'""

350-175'F 175-140'F 140-130'F 130'F 50'F 20'F 10'F 5'F HEATUP RATES TEMPERATURE-'EATUP IN ANY 1

HOUR PERIOD~""

140'F 140-155'F 155-190'F 190-350'F 10'F 20'F 30'F 50'F

-"Temperature range used should be based on the lowest RCS cold leg value.

~Temperature used should be based on lowest RCS cold leg value except when no RCP is in operation; then use an operating RHR heat exchanger outlet temperature.

SHEARON HARRIS UNIT 1

3/4 4-38 Amendment No.

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.4 At least one of the following Overpressure Protection Systems shall be OPERABLE:

a.

The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 2.9 square

inches, or b.

Two power-operated relief valves (PORVs) with setpoints which do not exceed the limits established in Figure 3.4-4.

APPLICABILITY:

MODE 4 when the temperature of any RCS cold leg is less than or equal to 325'F, MODE 5 and MODE 6 with the reactor vessel head on.

ACTION:

a.

With one PORV inoperable, restore the inoperable PORV to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 2.9 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b.

With both PORVs inoperable, depressurize and vent the RCS through at least a 2.9 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

c ~

In the event either the PORVs or the RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.

The report shall describe the circumstances initiating the transient, the effect of the PORVs or RCS vent(s) on the transient, and any corrective action necessary to prevent recurrence.

d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.9.4.1 Each PORV shall be demonstrated OPERABLE by:

a.

Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV actua-tion channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE; b

Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months; and c ~

Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORV is being used for overpressure protection.

Credit may only be taken for the setpoints when the RCS cold leg temperature

> 90'F.

SHEARON HARRIS UNIT 1

3/4 4-40 Amendment No.

~

~

~

I I

t i

I

)

~ l.

~

~l L

400 z

I 0

)K O

D 300 h

l MEASURED RCS TEMPERATURE (V)

RCS TEMP OF LOW PORV PSIG 0 HIGH PORV "

PSIG D 90 100 125 250 300 325 370 370 400 400 427 440 380 380 410 410 437 450 "8'ALUES BASED ON 5

EFPY REACTOR VESSEL DATA AND CONTAINS MARGINS OF -10'F AND +60 PSIG FOR POSSIBLE INSTRUMENT ERROR FIGURE 3.4-4 MAXIMUM ALLOWED PORV SETPOINT FOR THE LOW TEMPERATURE OVERPRESSURE SYSTEM SHEARON HARRIS - UNIT 1

3/4 4-41 Amendment No.

ql'v$

Cw

~

~

REACTOR COOLANT SYSTEM BASES PRES SURE/TEMPERATURE LIMITS (Con tinued )

b.

Figures 3.4-2 and 3.4-3 define limits to assure prevention of non-ductile failure only.

For normal operation, other inherent plant characteristics, e.g.,

pump heat addition and pressurizer heater capacity, may limit the heatup and cool down rates that can be achieved over certain pressure-temperature ranges.

2.

These limit lines shall be calculated periodically using methods pro-vided below, 3 ~

The secondary side of the steam generator must not be pressurized above 200 psig if the temperature of the steam generator is below 70'F, 4.

The pressurizer heatup and cooldown rates shall not exceed 100'F/h and 200'F/h, respectively.

The spray shall not be used if the tem-perature difference between the pressurizer and the spray fluid is greater than 625'F, and 5.

System preservice hydrotests and inservice leak and hydrotests shall be performed at pressures in accordance with the requirements of ASME Boiler and Pressure Vessel

Code,Section XI.

The fracture toughness testing of the ferritic materials in the reactor vessel was performed in accordance with the 1971 Winter Addenda to Section III of the ASME Boiler and Pressure Vessel Code.

These properties are then evaluated in accordance with the NRC Standard Review Plan.

Heatup and cooldown limit curves are calculated using the most limiting value of the nil-ductility reference temperature, RTNDT, at the end of 5 effective full power years (EFPY) of service life.

The service life period is chosen such that the limiting RTN>T at the 1/4T location in the core region is greater than the RTNDT of the limiting unirradiated material.

The selection of such a

limiting RTNDT assures that all components in the Reactor Coolant System will be operated conservatively in accordance with applicable Code requirements'he reactor vessel materials have been tested to determine their initial RTNDT; the results of these tests are shown in Table B 3/4.4-1.

Reactor operation and resultant fast neutron (E greater than 1 MeV) irradiation can cause an increase in the RTNDT.

Therefore, an adjusted reference temperature, based upon the

fluence, copper content, and nickel content of the material in question, can be predicted using Figure B 3/4.4-1 and the value of ARTNDT computed by Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials."

SHEARON HARRIS UNIT 1

B 3/4 4-7 Amendment No.