ML15112B092

Amends 119,119 & 116 to Licenses DPR-38,DPR-47 & DPR-55, Respectively,Revising Tech Specs Re Heatup,Cooldown & Inservice Test Limitations for RCS

ML15112B092
Person / Time
Site:	Oconee
Issue date:	03/11/1983
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Duke Power Co
Shared Package
ML15112B094	List: ML15112B092 ML15112B096 ML15112B098
References
DPR-38-A-119, DPR-47-A-119, DPR-55-A-116 NUDOCS 8303210009
Download: ML15112B092 (22)

Text

• oUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON,.D. C. 20655 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.119 License No. DPR-38

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Duke Power Company (the licensee) dated November 12, 1982, as supplemented February 24, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasona6le assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;.

D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-38 is hereby amended to read as follows:

3.B Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 119_, are hereby incorporated in the license. The licensee shall operate the facilityin accordance with the Technical Specifications.

83031009. 830311 DOCi 00026D P

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3. This license amendment becomes effective on March 14, 1983.

FOR THE NUCLEAR REGULATORY COMMISSION

o. F. Stolz, Chief Ope ating Reactors Branc

1. 4 Di ision of Licensing

Attachment:

Changes to the Technical Specifications MAR 11 1983 Date of Issuance:

o0 UNITED STATES EAR REGULATORY COMMISSION WASHINGTON,D.C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Mendment No.119 License No. DPR-47

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Duke Power Company (the licensee) dated November 12, 1982, as supplemented February 24, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission 's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of FAcility Operating License No. DPR-47 is hereby amended to read as follows:

3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 119 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

a

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3.

This license amendment becomes effective on March 14, 1983.

FOR THE NUCLEAR REGULATORY COMMISSION Job F. Stolz, Chief Op rating Reactors Branch #4 ivision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: MAR 11 1983

0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50- 287 OCONEE NUCLEAR STATION, UNIT NO.3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 116 License No. DPR-55

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Duke Power Company (the licensee) dated November 12, 1982, as supplemented February 24, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii)

.that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of FWility Operating License No. DPR-55 is hereby amended to read as follows:

3.B *Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

116, are hereby ingprporated in the license. The licensee shall operate the facility in.accordance with the Technical Specifications.

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3. This license amendment becomes effective on March 14, 1983.

FOR THE NUCLEAR REGULATORY COMMISSION J n. Stolz, Chief pe ting Reactors Branch #4 sion of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: MAR 11 1983 aw1

ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO. 119TO DPR-38 AMENDMENT NO. 19TO DPR-47 AMENDMENT NO.

116TO DPR-55 DOCKETS NOS.

50-269, 50-270 AND 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by amendment numbers and contain vertical lines indicating the area of change.

Remove Payes Insert Pages vi vi 3,1-3 3.1-3 3.1-3a 3.1-3a 3.1-5 3.1-5 3.1-5a 3.1-5b 3.1-6 3.1-6 3.1-6a 3.1-6a 3.l-6b 3.1-6b 3.1-7 3.1-7 3.1-7a 3.1-7a 3.1-7b 3.1-7b 3.1-7c 3.1-7c 3.1-7d 3.1-7d 3.1-7e 3.1-7e

LIST OF TABLES Table No.

Page 2.3-1A Reactor Protective System Trip Setting Limits - Unit 1 2.3-11 2.3-18 Reactor Protective System Trip Setting Limits - Unit 2 2.3-12 2.3-1C Reactor Protective System Trip Setting Limits -.Unit 3 2.3-13 3.1-1 Operational Guidance for Plant Heatup 3.1-5a 3.1-2 Operational Guidance for Plant Cooldown 3.1-5b 3.5-1-1 Instruments Operating Conditions 3.5-4 3.5-1 Quadrant Power Tilt Limits 3.5-14 3.7-1 Operability Requirements for the Emergency Power Switching 3.7-13 Logic Circuits 3.17-1 Fire Protection & Detection Systems 3.17-5 4.1-1 Instrument Surveillance Requirements 4.1-3 4.1-2 Minimum Equipment Test Frequency 4.1-9 4.1-3 Minimum Sampling Frequency 4.1-10 4.2-1 Oconee Nuclear Station Capsule Assembly Withdrawal Schedule 4.2-3 at Crystal River Unit No. 3 4.4-1 List of Penetrations with 10CFR50 Appendix J Test 4.4-6 Requirements 4.11-1 Oconee Environmental Radioactivity Monitoring Program 4.11-3 4.11-2 Offsite Radiological Monitoring Program 4.11-4 4.11-3 Analytical Sensitivities 4.11-5 4.17-1 Steam Generator Tube Inspection 4.17-6 6.1-1 Minimum Operating Shift Requirements with Fuel in Three 6.1-6 Reactor Vessels 6.6-1 Report of Radioactive Effluents 6.6-8 vi Amendments Nos.

9,

119, & 116

3.1.2 Pressurization, Heatup, and Cooldown Limitation Specification 3.1.2.1 The reactor coolant pressure and the system heatup and cooldown rates (with the exception of the pressurizer) shall be limited as follows:

Heatup:

Heatup rates and allowable combinations of pressure and tempera ture shall be limited in accordance with Table 3.1-1 and Figure 3.1.2-1A Unit 1 3.1.2-lB Unit 2 3.1.2-IC Unit 3 Cooldown:

Cooldown rates and allowable combinations of pressure and tempera ture shall be limited in accordance with Table 3.1-2 and Figure 3.1.2-2A Unit 1 3.1.2-2B Unit 2 3.1.2-2C Unit 3 3.1.2.2 Leak tests required by Specification 4.3 and ASME Section XI shall be limited to the heatup and cooldown rates and allowable combina tions of pressure and temperature provided in Tables 3.1-1, 3.1-2 and Figure 3.1.2-3A Unit 1 3.-1.2-3B Unit 2 3.1,2-3C Unit 3 3.1.2.3 For thermal steady state system hydro tests required by ASME Section XI the system may be pressurized to the limits set forth in Specification 2.2 and 3.1.2.2.

3.1.2.4 The secondary side of the steam generator shall not be pressurized above 237 psig if the temperature of the vessel shell is below 110oF.

3.1.2.5 The pressurizer heatup and cooldown rates shall not exceed 100aF/hr.

The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 410 0f.

Amendments Nos. 119,

119, 16 3.1-3

3.1.2.6 Prior to exceeding fifteen (Unit 1) fifteen (Unit 2) fifteen (Unit 3) effective full power years of operation.

Figures 3.1.2-iA (Unit 1), 3.1.2-2A (Unit 1) 3.1.2-1B (Unit 2), 3.1.2-2B (Unit 2) 3.1.2-iC (Unit 3), 3.1.2-2C (Unit 3) and 3.1.2-3A (Unit 1) 3.1.2-3B (Unit 2) 3.1.2.-3C (Unit 3) and Technical Specification 3.1.2.1, 3.1.2.2 and 3.1.2.3 shall be updated for the next service period in accordance with 10 CFR 50, Appendix G, Section V.B and V.E.

3.1.2.7 The updated proposed-technical specification referred to in 3.1.2.6 shall be submitted for NRC review at least 90 days prior to the end of the service period for Units 1, 2 and 3.

3.1-3a Amendments Nos. 119, 119, & 116

limitations of 110F and 237 psig are based on the highest estimated RT DT of +40aF and the preoperational system hydrostatic test pressure of 1312 psig.

The average metal temperature is assumed to be equal to or greater than the coolant temperature.

The limitations include margins of 25 psi and 100 F for possible instrument error.

The spray temperature difference is imposed to maintain the thermal stresses at the pressurized spary line nozzle below the design limit.

REFERENCES (1) Analysis of Capsule OCII-A from Duke Power Company Oconee Unit 2 Reactor Vessel Materials Surveillance Program, BAW-1699, December 1981.

(2) Analysis of Capsule.OCIII-B from Duke Power Company Oconee Unit 3 Reactor Vessel Naterials Surveillance Program, BAW-1697, October 1981.

(3) Analysis of Capsule OCI-E from Duke Power Company Oconee Unit I Reactor Vessel Materials Surveillance Program, BAW-1436, September, 1977.

Amendments Nos.

119,

119, & 116 3.1-5

TABLE 3.1-1 OPERATIONAL GUIDANCE FOR PLANT HEATUP I.

RC Temperature Constraints RC Temperature Maximum Heatup Rate T < 280aF 50oF/HR T > 280oF 100 0F/HR II. RC Pump Constraints None.

Amendments Nos.

1199

119, 116 3.1-5a

0 TABLE 3.1-2 OPERATIONAL GUIDANCE FOR PLANT COOLDOWN I. RC Temperature Constraints RC Temperature(1)

Maximum Cooldown Rate(2)

T > 280aF

< 50oF in any hour period 150 0F < T < 280aF

< 250 F in any hour period T < 150 0F

< 10oF in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized(3)

< 50oF in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period (1) RC temperature is cold leg temperature if one or more RC pumps are in operation or if on natural circulation cooldown; otherwise it is the LPI cooler outlet temperature.

(2) These rate limits must be applied to the change in temperature indicatioti from cold leg temperature to LPI cooler outlet tempera ture per Note (1).

(3) When the RCS is depressurized such that all three of the following conditions exist:

a)

RCS temperature < 200 0F, b)

RCS pressure < 50 psig, c)

All RC Pumps off, the maximum cooldown rate shall be relaxed to < 500F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.

II.

RC Pump Constraints For Validity of Guidance RC Temperature Allowed Pump Combinations

> 270OF

-Any 270-2000F No more than 1 pump per loop

< 200 0 F No more Aan 1 pump Amendments Nos. 119,

116 3.1-5b

rD (D

CA THE REGIONS OF ACCEPTABLE OPERATION ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVES.

MARGINS ARE INCLUDED FOR THE PRESSURE DIFFERENTIAL BETWEEN POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE. MARGINS OF 25 PSIG AND 10oF ARE INCLUDED FOR POSSIBLE INSTRUMENT ERROR. THE REACTOR MUST NOT BE MADE CRITICAL UNTIL THE PRESSURE-TEMPERATURE COMBINATIONS ARE TO THE RIGHT OF THE CRITICALITY LIMIT CURVE.

2250 M

R POINT TEMP.

PRESS.

A 70 359 2000 a

110 375 C

160

'24 D

185 466 E

210 526 L

1750F 240 526 G

242 650 H

260 740 1500 I

285 919 J

310 1107 4

)

K 335 1385 K

P CL 360 1790 1250 M

ass 225o 0

0

_0 0

N 368 0

01 <_0 368 1303 P

375 1386 o

1000 0oo 179o 00 425 2250I CRITICALITY LIMIT C2.. j 750 G

+j 500 o

-aA a

F 250 0

N I

II 60 100 1110 180 220 260 300 340 380 420 Indicated Reactor Coolant System Temperature, Tc,oF UNIT I OCONEE NUCLEAR STATION REACTOR COOLANT SYSTEM NORMAL OPERATION-HEATUP LIMITATIONS APPLICABLE FOR THE FIRST IS EFPY Figure 3.1.2-1A

CD

0.

(D C,)

0 THE REGIONS OF ACCEPTABLE OPERATION ARE BELOW AND TO THE RIGHT-OF THE LIMIT CURVES.

MARGINS ARE INCLUDED FOR THE PRESSURE DIFFERENTIAL BETWEEN POINT OF SYSTEM PRESSURE o

2250 MEASUREMENT AND THE PRESSURE ON TgE REACTOR VESSEL REGION CONTROLLING THE LtMIT R

CURVE.

MARGINS OF 25 PSIG AND 10 F ARE INCLUDED FOR POSSIBLE INSTRUMENT H

ERROR.

THE REACTOR MUST NOT BE HADE CRITICAL UNTIL THE PRESSURE-TEMPERATURE COMBINATIONS ARE TO THE RIGHT OF THE CRITICALITY LIMT CUiVE.

e2000 1750 POINT TEMP.

PRESS.

A 70 352 L

91 363 C

125 385 1 5 0 0 3 63au.

o D

148 409 ScoE 170 443 K

F 204 521 a

1250

/

K P

G 240 521 0

H 212 670 0

272 849 J

299 1066 1000 K

322 1289 L ~L 345 1608 00 I

M 378 2250 O

_j N

360 0

750 0

360 1271 P

362 1289 F0 385 1608 CRITICALITY R

418 2250 A

B C

DG LIMIT T.3 250 0

I I

I I

I N

I 60 100 140 180 220 260 300 340 380 420 Indicated Reactor Coolant Systdfil Temperature, Tc,oF UNIT 2 OCONEE NUCLEAR STATION REACTOR COOLANT SYSTEM NORMAL OPERATION HEATUP LIMITATIONS APPLICABLE FOR FIRST 15.0 EFPY Figure 3.1.2-1B

(D 0 Ln THE REGIONS OF ACCEPTABLE OPERATION ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVES.

MARGINS ARE INCLUDED FOR THE PRESSURE DIFFERENTIAL BETWEEN POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE 2250 0

ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE.

MARGINS OF 25 PSIG AND 10 F ARE N

S INCLUDED FOR POSSIBLE INSTRUMENT ERROR. THE REACTOR 1slST NOT BE MADE CRITICAL UNTIL THE 2000 -

PRESSURE-TEMPERATURE COMBINATIONS ARE TO THE RIGHT OF THE CRITICA ITY LIMIT CURVE.

M R

POINTS TEMP PRESS A

70 326 B

125 326 S1500 C

118 348 L L9 D

170 396

>1 U)E 193 q68 1250

.p F

213 521

0.

0 240 521 K

H 242 625 4a I

272 790 o.-

J 299 983 o3I000 C-) MCRITICALITY K

322 1182 0

L 345 1466 o -

LIMIT M

367 1860 750 N

386 2250 0

370 0

p P

370 1286 9

385 1466 500-E 107 1860 G

S 26 2250 250 I

I I

I 0

60 100 140 180 220 260 300 340 380 420 460 Indicated Reactor Coolant System Temperature, Tc, OF UNIT 3 OCONEE NUCLEAR STATION REACTOR COOLANT SYSTEM NORMAL OPERATION-HEATUP LIMITATIONS APPLICABLE FOR FIRST 15.0 EFPY Figure 3.1.2-1C

C+

(A 0

THE REGIONS OF ACCEPTABLE OPERATION ARE BELOW AND TO THt RIGHT OF THE LIMIT CURVES.

MARGINS ARE INCLUDED FOR THE PRESSURE DIFFERENTIAL BETWEEN POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE.

on MARGINS OF 25 PSIG AND 16 F ARE INCLUDED FOR POSSIBLE INSTRUMENT ERROR.

01

-a 2 250 2000 POINT TEMP PRESS A

70 368 1750 H

s s

E-150B 160 368 C

185 436

'D 210 515 E

235 654 1500 F

260 862 G

290 1136 H

330 1774

-0 1250 I

350 2250 CL G

L.

0 0

0 1000 F

ra 750 41)E e

E 500 c

250 0

I I

IIIII 60 100 140 180 220 260 300 310 380 420 Indicated Reactor Coolant System Temperature, Tc, oF UNIT I OCONEE NUCLEAR STATION REACTOR COOLANT SYSTEM NORMAL OPERATION Figure 3.1.2-2A COOLDOWN LIMITATIONS APPLICABLE FOR FIRST 15 EFPY

(D CL (D

0 CA THE REGIONS OF ACCEPTABLE OPERATION ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVES. MARGINS ARE INCLUDED FOR THE PRESSURE DIFFERENTIAL BETWEEN POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION 2250

-CONTROLLING THE LIMIT CURVE. MARGINS OF 25 PSIG AND 10aF ARE INCLUDED FOR POSSIBLE INSTRUMENT ERROR.

2000 H

4) 1750 S1500 POINT TEMP.

PRESS.

co m

A 70 375 8

160 375 1250 C

185 53 6

D 210 538 o:+

E 235 688 8

100-F 260 911 100091 CL

~F G

290 1191 00 H

330 1877 oI 347 2250 750 E

E D

500 A

C 250 0

I I

I I

I II 60 100 1 140 180 220 260 300 340 380 420 Indicated Reactor Coolant System Temperature, Tc, OF UNIT 2 OCOMEE NUCLEAR STATION REACTOR COOLANT SYSTEM NORMAL OPERATION-COOLDOWN LIMITATIONS APPLICABLE FOR FIRST 15.0 EFPY Figure 3.1.2-2B

THE REGIONS OF ACCEPTABLE OPERATION ARE BELOW AND TO THE RIGHT OF THE LIMIT (IIF CURVES.

MARGINS ARE INCLUDED FOR THE PRESSURE DIFFERENTIAL BETWEEN POINT OF 2250 SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION I

CONTROLLING THE LIMIT CURVE.

MARGINS OF 25 PSIG AND 10oF ARE INCLUDED FOR S2000-POSSIBLE INSTRUMENT ERROR.

1750 1500 1250-POINTS TEMP PRESS

-41 0

A 70 360 B

160 360 C

185 425 F

D 210 497 o 0 a 750-E 235 629 CU E

F 260 828 D

G 290 1095

-0 500 -

c 5

A%

B H

330 1705 1

351 2250 250 0

1 I

I I

I II 60 100 140 180 220 260 300 340 380 420 Indicated Reactor Coolant System Temperature, Tc, OF UNIT 3 OCONEE NUCLEAR STATION REACTOR COOLANT SYSTEM NORMAL OPERATION-COOLDOWN LIMITATIONS APPLICABLE FOR FIRST 15.0 EFPY Figure 3.1.2-2C

2500 THE REGIONS OF ACCEPTABLE OPERATION ARE BELOW AND TO THE RIGHT OF THE LIMIT K

CURVES. MARGINS ARE INCLUDED FOR THE PRESSURE DIFFERENTIAL BETWEEN POINT OF o rn SYSTEM PRESSURE MEASUREMENT AND'THE PRESSURE ON THE REASTOR VESSEL REGION 2250

-CONTROLLING THE LIMIT CURVE. MARGINS OF 25 PSIG AND 16 F ARE INCLUDED FOR

a.

POSSIBLE INSTRUMENT ERROR.

2000 1750 E

Ij 1500

-I 1250 H

POINT TEMP.

PRESS.

A 70 509 o

B 160 509 Cn 1000 G

C 165 526 o

D 215 526 F

E 219 764

_j F

235 861 E

G 260 1028 H

285 1266 I

310 1517 eA BC J

335 1888 500 K

368 2500

-~

250 0

III I

I I

I I

60 100 140 180 220 260 300 340 380 420 Indicated Reactor Coolant System Temperature, Tc, OF UNIT I OCONEE NUCLEAR STATION REACTOR COOLANT SYSTEM INSERVICE LEAK AND Figure 3.1.2-3A HYDROSTATIC TEST HEATUP AND COOLDOWN LIMITATION APPLICABLE FOR FIRST 15.0 EFYP

(D 050 THE REGIONS OF ACCEPTABLE OPERATION ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVES. MARGINS ARE INCLUDED FOR THE PRESSURE DIFFERENTIAL BETWEEN 2250 POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR 50 VESSEL REGION CONTROLLING THE LIMIT CURVE. MARGINS OF 25 PSIG AND 10oF ARE INCLUDED FOR POSSIBLE INSTRUMENT ERROR.

2000 LWL 1750 H

3 50POINTS TEMP PRESS I1500 A

70 519 L-

.8 120 521 1250 C

215 521 0

219 795 0

E 249 980 o

F F

272 1176 G

299 1465 Lo0 1000 0

0E o

E H

322 1762 I

345 2108 (4 0 750 D

J 360 2500 500 A

o A

B C

250 0

I I

IIII I

I I

60 100 140 180 220 260 300 340 380 420 Indicated Reactor Coolant System Tempepature, Tc,or UNIT 2 OCONEE NUCLEAR STATION REACTOR COOLANT SYSTEM INSERVICE LEAK AND HYDROSTATIC TEST HEATUP AND COOLDOWN LIMITATIONS APPLICABLE FOR 15.0 EFPY Figure 3.1.2-3B

CL 0

(A o

2500 THE REGIONS OF ACCEPTABLE OPERATION ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVES.

L o0 2250 -MARGINS ARE INCLUDED FOR THE PRESSURE DIFFERENTIAL BETWEEN POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON lHif REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE. MARGINS OF 25 PSIG AND 10o F ARE INCLUDED FOR POSSIBLE INSTRUMENT ERROR.

cn 2000 K

POINTS TEMP PRESS A

70 499 1750 160 499 C

166 521 D

215 521 1

-I500 E

e 5

E 218 738

.m I

F 238 855 I 1250 249 923 H2H 272 1097 CH 4

299 1354 0

G J

322 1619 F

K 345 1998 0

7 E

L 370 2500

.~

750 20 e

A CD 500 250 0

60 100 140 180 220 260 300 340 380 420 Indicated Reactor Coolant System Temperature, Tc, OF UNIT 3 OCONEE NUCLEAR STATION REACTOR COOLANT SYSTEM INSERVICE LEAK AND HYDROSTATIC TEST HEATUP & COOLDOWN LIMITATIONS FOR FIRST Figure 3.1.2-3C 15.0 EFPY