ML16134A673

Proposed Tech Spec Changes Re Core Protection Safety Limits, Protective Sys Max Allowable Setpoints & Rod Position Limits

ML16134A673
Person / Time
Site:	Oconee
Issue date:	05/03/1982
From:	DUKE POWER CO.
To:
Shared Package
ML15222A069	List: ML15222A068 ML16134A673 ML20052F240
References
NUDOCS 8205120269
Download: ML16134A673 (24)

Text

Attachment 1 Duke Power Company Oconee Nuclear Station Proposed Technical Specification Revision Oconee 3, Cycle 7 Pages 2.1-3d 3.5-20a 2.1-6

.3.5-20b 2.1-9 3.5-20c 2.1-12 3.5-20d 2.3-10 3.5-20e 3.2-2 3.5-23 3.5-9 3.5-23a 3.5-17 3.5-23b 3.5-17a 3.5-26 3.5-17b 3.5-26a 3.5-20 3.5-26b

• 301-29 8

DR iI0

2.

The combination of radial and axial peak that causes central fuel melting at the hot spot. The limit is 20.15 kw/ft for Unit 3.

Power peaking is not a directly observable quantity, and, therefore, limits have been established on the bases of the.reactor power imbalance produced by the power peaking.

The specified flow rates for Curves 1, 2 and 3 of Figure 2.1-3C~correspond to the expected minimum flow rates with four pumps, three pumps and one pump in each loop, respectively.

The magnitude of the rod bow penalty applied to each fuel cycle is equal to or greater than the necessary burnup independent DNBR rod bow penalty for the ap plicable cycle minus a credit of 1% for the flow area reduction factor used in the hot channel analysis. All plant operating limits are based on a minimum DNBR criteria of 1.30 plus the amount necessary to offset the reduction in DNBR due to fuel rod bow. (4)

The maximum thermal power for three-pump operation is 90.65 percent due to a power level trip produced by the flux-flow ratio 74.7 percent flow x 1.08 =

80.7 percent power plus the maximum calibration and instrument error (Reference 4).

The maximum thermal power for other coolant pump conditions are produced in a similar manner.

For each curve of Figure 2.1-3C a pressure-temperature point above and to the left of the curve would result in a DNBR greater than 1.30 or a local quality at the point of minimum DNBR less than 22 percent for that particular reactor coolant pump situation. The curve of Figure 2.1-1C is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3C.

References (1) Correlation of Critical Heat Flux in a Bundle Cooled by Pressurized Water, BAW-10000, March 1970.

(2) Oconee 3, Cycle 3 - Reload Report - BAW-1453, August, 1977.

(3) Amendment 1 -

Oconee 3, Cycle 4 -

Reload Report -

BAW-1486, June 12, 1978.

(4) Oconee 3, Cycle 7 -

Reload Report -

DPC-RD-2001, April 1982.

2.1-3d

2400 ACCEPT BLE OPERAT ON 2200 2000 0

C) 0 1800 UNACCEPTABLE OPERATION 1600 580 600 620 640 660 Reactor Coolant Core Outlet Temperature,oF CORE PROTECTION SAFETY LIMITS UNIT 3 mOEm OCONEE NUCLEAR STATION Figure 2.1-1c 2.1-6

0~---

Thermal Power Level, %

120 M1=0.638

-36.5,112.0) 112.0 (33.0,112.0)

-110

(-49.5,103.70)

I ACCEPTABLE 4 PUMP OPERATION

-100 M2=-1.864

.90.65I

(-49.5,82.35)

ACCEPTABLE8 OPERATION 8

-70 1

63.26

(-49.5,54.90) 2ACCEPTABLE 60 (49.5,59.90) 2,3,&4 PUMP OPERATION

-50

-40I JNACCEPTABLE OPERATION

.R3I (49.5,32.51)

.I-2 2 I

UNACCEPTABLE Lq OPERATION cc 0

L 10 R0

-60

-50

-40

-30

-20

-10 0

10 20 30 40 50

-60 Reactor Power Imbalance, %

CORE PROTECTION SAFETY LIMITS UNIT 3 OCONEE NUCLEAR STATION Figure 2.1-2C 2.1-9

2400 ACCEPTABLE OPERAT ON 2200 4 PUMP 2000 o

/

PUMP w

2 3 PUMP/

0 1800 UNACC PTABLE OPERA ION 1600 580 600 620 640 660 Reactor Coolant Core Outlet Temperature, OF PUMPS COOLANT POWER TYPE OF LIMIT OPERATING FLOW (GPM)

(% FP) 4 374,880(100%)

112.0 DNBR 3

280,035(74.7%)

90.7 DNBR 2

183,690(49.0%)

63.63*.

DNBR/QUALITY CORE PROTECTION SAFETY LIMITS UNIT 3 E~POWE OCONEE NUCLEAR STATION Figure 2.1-3C 2.1-12

Thermal Power Level, %

- 120

(-16.0,108.0) 108.0

-110 (16.5,108.0)

ACCEPTABLE 4 M1=0.992 PUMP OF ERATION M2=-1.890 100

(-33.5,90.64)

.90 UNACCEPTABLE

- oU OPERATION ACCEP BLE 3&4 I PUMP 0 ERATION (33.5,75.94)

I

- 70

(-33.5,63.31)

UNACCEPTABLE 60 OPERATION Kill,52.92

-50 (31,4.1 ACCEPTABLE 2,3,&4 (33.5,48.61)

I PUMP OPERATION I 30

- 20 (33.5,20.86) 1-10I C,,)

I, It

-50

-40

-30

-20

-10 0

10 20 30 40 50 Reactor Power Imbalance, %

PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINTS UNIT 3 UKEPOWER OCONEE NUCLEAR STATION Figure 2.3-2C 2.3-10

Bases The high pressure injection system and chemical addition system provide con trol of the reactor coolant system boron concentration.(1) This is normally accomplished by using any of the three high pressure injection pumps in series with a boric acid pump associated with either the boric acid mix tank or the concentrated boric acid storage tank. An alternate method of boration will be the use of the high pressure injection pumps taking suction directly from the borated water storage tank.(2)

The quantity of boric acid in storage in the concentrated boric acid storage tank or the borated water storage tank is sufficient to borate the reactor coolant system to a 1% Ak/k subcritical margin at cold conditions (706F) with the maximum worth stuck rod and no credit for xenon at the worst time in core life. The current cycles for each unit, Oconee 1, Cycle 7, Oconee 2, Cycle 6, and Oconee 3, Cycle 7 were analyzed with the most limiting case selected as the basis for all three units.

Since only the present cycles were analyzed, the specifications will be re-evaluated with each reload. A minimum of 1020 ft3 of 8,700 ppm boric acid in the concentrated boric acid storage tank, or a minimum of 350,000 gallons of 1835 ppm boric acid in the borated water storage tank (3) will satisfy the requirements. The volume requirements include a 10%

margin and, in addition, allow for a deviation of 10 EFPD in.the cycle length.

The specification assures that two supplies are available whenever the reactor is critical so that a single failure will not prevent boration to a cold con dition. The required amount of boric acid can be added in several ways. Using only one 10 gpm boric acid pump taking suction from the concentrated boric acid storage tank would require approximately 12.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to inject the required boron. An alternate method of addition is to inject boric acid from the borated water storage tank using the makeup pumps. The required boric acid can be injected in less than six hours using only one of the makeup pumps.

The concentration of boron in the concentrated boric acid storage tank may be higher than the concentration which would crystallize at ambient conditions.

For this reason, and to assure a flow of boric acid is available when needed, these tanks and their associated piping will be kept at least 10aF above the crystallization temperature for the concentration present. The boric acid concentration of 8,700 ppm in the concentrated boric acid storage tank cor responds to a crystallization temperature of 770 F and therefore a temperature requirement of 870F. Once in the high pressure injection system, the concen trate is sufficiently well mixed and diluted so that normal system temperatures assure boric acid solubility.

REFERENCES (1) FSAR, Section 9.1; 9.2 (2) FSAR, Figure 6.2 (3) Technical Specification 3.3 3.2-2

f.

If the maximum positive quadrant power tilt exceeds the Maximum Limit of Table 3.5-1, the reactor shall be shut down within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Subsequent reactor.operation is permitted for the purpose of measurement, testing, and corrective action provided the ther mal power and the Nuclear Overpower Trip Setpoints allowable for the reactor coolant pump combination are restricted by a reduc tion of 2% of thermal power for each 1% tilt for the maximum tilt' observed prior to shutdown.

g.

Quadrant power tilt shall be monitored on a minimum frequency of once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during power operation above 15% full power.

3.5.2.5 Control Rod Positions

a.

Technical Specification 3.1.3.5 does not prohibit the exercising of individual safety rods as required by Table 4.1-2 or apply to inoperable safety rod limits in Technical Specification 3.5.2.2.

b.

Except for physics tests, operating rod group overlap shall be 25% t 5% between two sequential groups.

If this limit is ex ceeded, corrective measures shall be taken immediately to achieve an acceptable overlap.. Acceptable overlap shall be attained within two hours or the reactor shall be placed in a hot shutdown condition within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

C.

Position limits are specified for regulating.and axial power shaping control rods.

Except for physics 'tests or exercising control rods, the regulating control rod insertion/withdrawal limits are specified on figures 3.5.2-lAl, 3.5.2-1A2, and 3.5.2-1A3 (Unit 1); 3.5.2-IBI, 3.5.2-1B2, and 3.5.2-1B3 (Unit 2);.3.5.2-I1, 3.5.2-1C2 and 3.5.2-103 (Unit 3) for four pump operation, on figures 3.5.2-2A1, 3.5.2-2A2, and 3.5.2-2A3 (Unit 1); 3.5.2-2B1, 3.5.2-2B2, and 3.5.2-2B3 (Unit 2); figures 3.5.2-2C1, 3.5.2-2C2, and 3.5.2-2C3 (Unit 3) for three pump operation, and on figures 3.5.2-2A4, 3.5.2-2AS, and 3.5.2-2A6 (Unit 1); 3.5.2-2B4, 3.5.2-2B5, and.3.5.2-2B6 (Unit 2); figures 3.5.2-2C4, 3.5.2-2C5, and 3.5.2-2C6 (Unit 3) for two pump operation. Also, excepting'physics tests or exercising control rods, the axial power shaping control rod insertion/withdrawl limits are specified on'figures 3.5.2-4A1, 3.5.2-4A2, and 3.5.2-4A3 (Unit 1); 3.5.2-401, and 3.5.2-4B2, and 3.5.2-4B3, (Unit 2); 3.5.2-4G1 and 3.5.2-4C2 (Unit 3).

If the control rod position limits are exceeded, corrective measures shall be taken immediately to achieve an accpetable control rod position. An acceptable control rod position shall then be attained within two hours. The minimum shutdown margin required by Specification 3.5.2.1 shall be maintained at all times.

3.5-9

(300,102) 100-(150,102)

(280,102)

(275,92) 80-SHUTDOWN MARGIN (270,80)

LIMIT RESTRICTED OPERATION LL.

60.

LU 3:

UNACCEPTABLE o0 OPERATION (90,50)

(200,50) 0 40 LU ACCEPTABLE OPERATION 20 (40,15)

(90,15)

(0,10Q):

.(0,5) 0 50 100 150 200 250 300 ROD INDEX,%WD ROD POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 0 TO 50 (+10, -0) EFPD UNIT 3 0UKEPOWE OCONEE NUCLEAR STATION Figure 3.5.2-ICI 3.5-17

100-(150,102)

(275,102) (300,102 SHUTDOWN (260,92)

MARGIN LIMIT 80-(250,80)

RESTRICTED OPERATION UNACCEPTABLE 60-OPERATION O

0 (90,50)(200,50) 40 ACCEPTABLE OPERATION 20 (40,15)

(90,15)

(0,10)

(0,5) 0 50 100 150 200 250 300 ROD INDEX,%WD ROD POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 50 (+10, -0) TO 200 (+/-10) EFPD UNIT 3 sUEPgE4 OCONEE NUCLEAR STATION Figure 3.5.2-1C2 3.5-17a

0 (300,102) 100 (220,102)

(275,102)

(260,92)

(250,80)

UINACCEPTABLE RESTRICTED OPERATION OPERATION U.

f 60 (160,50)

(200,50) 0 SHUTDOWN ACCEPTABLE MARGIN OPERATION LIMIT 20 (100,15)

(0,5) 0 I

0 50 100 150 200 250 300 ROD INDEX,%WD ROD POSITION LIMITS FOR FOUR-PUMP OPERATION AFTER 200 (+10) EFPD UNIT 3 mUm OCONEE NUCLEAR STATION Figure 3.5.2-1C3 3.5-17b

100 80 (130,77)

(263,77)

(300,77)

CL o

v60 WU UNACCEPTABLE OPERATION RESTRICTED (90,50)

OPERATION (200,50) 0 S40 SHUTDOWN MARGIN ACCEPTABLE LIMIT OPERATION 20 (30,15)

(90,15)

(0,10)

(0,5) 0 50 100 150 200 250 300 ROD INDEX,%WD ROD POSITION LIMITS FOR THREE-PUMP OPERATION FROM 0 TO 50 (+10, -0) EFPD UNIT 3 OCONEE NUCLEAR STATION Figure 3.5.2-2C1 3.5-20

100 80

((300,77) 80-

~(130,77)

(24 5,77)

(0 7

UNACCEPTABLE 60 OPERATION LU RESTRICTED 5

OPERATION (90,50)

(0,0 0

0 40 SHUTDOWN MARGIN LIMIT ACCEPTABLE OPERATION 20 (30,15)

(90,15)

(0,10)

(0,5) 0 0

50 100 150 200 250 300 ROD INDEX,%WD ROD POSITION LIMITS FOR THREE-PUMP OPERATION FROM 50 (+10, -0) TO 200 +/-10 EFPD UNIT 3 UKEIOWE OCONEE NUCLEAR STATION Figure 3.5.2-2C2 3.5-20a

100 RESTRICTED OPERATION 80 -(210,77)

(300,77)

(245,77) 6 s U

3 (16050)

UNACCEPTABLE OPERATION S40 LU SHUTDWN ACCEPTABLE MARGINOPERATION LIMIT.

20 (100,15)

(0,5)1 0

50 100 150 200-250 300 ROD INDEX,%WD ROD POSITION LIMITS FOR THREE-PUMP OPERATION AFTER 200 +/-10 EFPD UNIT 3 anPown OCONEE NUCLEAR STATION Figure 3.5.2-2C3 3.5-20b

100 80 U.

a60 (80,2)

(205,52)

(300,52) o (80.52)

(200,50) 0 40 SHUTDOWN RESTRICTED TMARGIN OPERATION LIMIT ACCEPTABLE OPERATION 20-UNACCEPTABLE OPERATION (50,15)

(90,15)

(0,10)4 (0,5)oe 0

50 100 150 200 250 300.

ROD INDEX,%WD ROD POSITION LIMITS FOR TWO-PUMP OPERATION FROM 0 TO 50 (+10, -0) EFPD UNIT 3 oumE OCONEE NUCLEAR STATION Figure 3.5.2-2C4 3.5-20c

100 80 U.

-60 U.j (8052 (203,52)

(300,52) cm (200,50) 0 0.

LU SHUTDOWN RESTRICTED MAIRGIN

/

OPERATION

'ACCEPTABLE

-LIMIT.

OPERATION

20.

UNACCEPTABLE OPERATION (5,)

(0,10)<

(0,5)<

0 50 100 150 200 250 300 ROD INDEX,%WD ROD POSITION LIMITS FOR TWO-PUMP OPERATION FROM 50 (+10, -0) TO 200 +/-10 EFPD UNIT 3 KEPOWEll OCONEE NUCLEAR STATION Figure 3.5.2-2C5 3.5-20d

100 80 RESTRICTED 2 OPERATION (170,52)

(203.52)

(300,52 UNACCEPTABLE (200,50) o OPERATION 40 SHUTDOWN ACCEPTABLE MARGIN OPERATION LIMIT 20 (110, 15)

(0,5) 0 50 100 150 200 250 300 ROD INDEX,%WO ROD POSITION LIMITS FOR TWO-PUMP OPERATION AFTER 200 +/-10 EFPD UN IT 3 tlEOEOCONEE NUCLEAR STATION Figure 3.5.2-2C6 3.5-20e

REACTOR POWER,%FP

(-21.3,102.0)

(25.0,102.0)

- 100

(-25.0,92.0)

ACCEP rAB LE (30.0,92.0)

OPER TION

(-30.0,80.0) 80 60 RESTRICTED OPERATION RESTR ITED OPERATION 40 20

-100

-80

-60

-40

-20 0

20 40 60 80 100 IMBALANCE,%

OPERATION POWER IMBALANCE ENVELOPE FROM 0 TO 50 (+10, -0) EFPD UNIT 3 neOWE OCONEE NUCLEAR STATION Figure 3.5.2-3C1 3.5-23

S7a REACTOR POWER,%FP

(-28.9,102.0) 1 (25.0,102.0) 100 ACCEPrABLE

(-31.8,92.0)

AC EPA (30.0,92.0)

OPERATION 80 60 RESTRICTED OPERATION RESTRICTED OPERATION 40 20

-100

-80

-60

-40

-20 0

20 40 60 80 100 IMBALANCE,%

OPERATIONAL POWER IMBALANCE ENVELOPE FROM 50 (+10, -0) TO 200 *100 EFPD UNIT 3 urEliWU OCONEE NUCLEAR STATION Figure 3.5.2-3C2 3.5-23a

REACTOR POWER,%FP

(-30.0,102.0)

(25.0,102.0)

-100 ACCEP"ABLE

(-32.7,92.0)

ACPE (30.0,92.0)

OPERATION

- 80

- 60 RESTRICTED OPERATION RESTRICTED OPERATION

- 40 20

-100

-80

-60

-40

-20 0

20 40 60 80 100 IMBALANCE,%

OPERATIONAL POWER IMBALANCE ENVELOPE AFTER 200 +10 EFPD UNIT 3 UKEPOWE OCONEE NUCLEAR STATION Figure 3.5.2-3C3 3.5-23b

(2.5,92) 80 (0,80)

(40,80)

RESTRICTED OPERATION S60 (6,0 O

ACCEPTABLE OPERATIONO

< 40 -(100,40) 20 0

20 40 60 80 100 APSR POSITION,%WD APSR POSITION LIMITS FOR OPERATION FROM 0 TO 200 +10 EFPD UNIT 3 ua OCONEE NUCLEAR STATION Figure 3.5.2-4CI 3.5-26

100 -

(40,102)

(2.5,92) 80 (0,80)

(40,80)

RESTRICTED OPERATION 60.

(60,60)

U 6020

,460810 0

0 RACCEPTABLE OPERATION

< 40-0,0 20 0

20 40 60 80 100 APSR POSITION,%Wo APSR POSITION LIMITS FOR OPERATION AFTER 200 +/-10 EFPD UNIT 3 ouKPower OCONEE NUCLEAR STATION Figure 3.5.2-4C2 3.5-26a

Figure 3.5.2-4C3 Deleted during Oconee Unit 3, Cycle 7 Operation 3.5-26b Duke Power Company Oconee Nuclear Station Oconee Unit 3, Cycle 7 Reload Report DPC-RD-2001 April 1982