ML17299B257

From kanterella
Jump to navigation Jump to search
Proposed Tech Spec Table 3.3-1, Reactor Protective Instrumentation, Allowing Facility to Remain at Power While Corrective Steps Implemented to Change Setpoint Settings
ML17299B257
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 05/28/1986
From:
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17299B256 List:
References
TAC-61574, TAC-61575, NUDOCS 8606020246
Download: ML17299B257 (3)


Text

TABLE 3. 3-1 REACTOR PROTECTIVE INSTRUHENTATION

(

m HINIHUH CD rn TOTAL NO. CHANNELS CHANNELS APPLIC/BLE FUNCTIONAL UNIT OF CHANNELS TO TRIP . OPERABLE HODES ACTION A- I. TRIP GENERATION A. Process

1. Pres s uri zer Press ure - High 4 2 3 1 2 2¹ 3¹ 2.
3. -

Pressurizer Pressu"e Steam Low Generator Level - . Low 4

4/SG 2 (b) 2/SG 3

3/SG 1

1 2

2 2¹ 2¹ 3¹ -]

4. Steam Generator Level - High 4/SG 2/SG 3/SG 1 2 3¹
5. Steam Generator Pressure - Low 4/SG 2/SG 3/SG 1, 2, 3", 4" 2¹
6. Containment Pressure High 4 2 3 1 2 2¹ 3¹ F-PTI 38¹ 9m~

~>

7. Reactor Coolant Flow Low 4/SG 2/SG 3/SG 2 ~8 1

4I

8. Local Power Density - High 4 2 ( )(d) 3 1 2 2 y 3

¹ Cg .9 . DNBR Low 4 2 (c)(d) 3 1, 2 2" 3" B. Excore Neutron Flux

1. Variable Overpower Trip 1 2 3¹ Logarithmic Power Level - High m 2.
a. Startup and Operating 2 (a)(d) 3 1, 2 2¹ 2 3 3'4 4* 5* 8
b. Shutdown 0 2 3,4,5 4 C. Core Protection Calculator System
1. CEA Calculators 1 2 (e) 1, 2 6, 7
2. Core Protection Calculators 2 (c)(d) 3 1, 2 8bOb02024b 8b0528 PDR ADQCK 05000528

,P PDR

CClTRQLLED BY USER TABLE 3. 3-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION ACTION STATEMENTS

2. Within 4 hours:

a) All full length and part length CEA groups are withdrawn to and subsequently maintained at the "Full Out" position, except during surveillance testing pursuant to the requirements of Specifi-cation 4. 1.3. 1.2 or for control when CEA group S may be inserted no further than 127.5 inches withdrawn.

b) The "RSPTlCEAC Inoperable" addressable constant in the CPCs is set to be indicated that both CEAC's are inoperable.

c) The Control Element Drive Mechanism Control System (CEDHCS) is placed in and subsequently maintained in the "Standby" mode except during CEA group S motion permitted by a) above, when the CEDHCS may be .operated in either the "Manual Group" or "Manual Individual" mode.

3. At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all full length and par t length CEAs are verified fully withdrawn except during surveillance testing pursuant to Specifica-tion 4. 1. 3. 1. 2 or during insertion of CEA group 5 by 2.a) above, then verify at least once as'ermitted per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that the inserted CEAs are aligned within 6.6 inches (indicated position) of all other CEAs in its group.
4. Following a CEA misalignment with both CEAC's and COLSS inoperable, operation may continue provided that within 1 hour:

The power is reduced to 85% of the pre-misaligned power but need not be reduced to less than 50% of RATED THERMAL POWER. This power restriction replaces the power restriction of Specification 3. 1. 3. 1, Figure 3. 1-2B, otherwise Specification 3. 1.3. 1 remains applicable.

ACTION 7 - With three or more auto restarts, excluding periodic auto restarts (Code 30 and Code 33), of one non-bypassed calculator during a 12-hour interval, demonstrate calculator OPERABILITY by performing a CHANNEL FUNCTIONAL TEST within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 8 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore an inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open an affected reactor trip breaker within the next hour

- UNIT 2 mWSP~ 3/4 3-9 PALO VERDE CONTRQLLED BY USER

A ~

A ~

~ t I

~ A

~ @

r p