ML20011A777

Proposed Tech Spec Pages 3/4 3-37 & 3/4 3-38 & Table 3.3-10 Re post-accident Monitoring Instrumentation

ML20011A777
Person / Time
Site:	Crystal River
Issue date:	10/28/1981
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20011A776	List: ML20011A775 ML20011A777
References
RTR-NUREG-0578, RTR-NUREG-578 TAC-47117, NUDOCS 8111030150
Download: ML20011A777 (3)

Text

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TECHNICAL SPECIFICATION CHANGE REQUEST-NO. 71 (Appendix A)

Delete pages 3/4' 3-37 and 3/4 3-38 and add revised pages 3/4 3-37 and 3/4 3-38.

Proposed Change This proposed change would clarify Technical Specification 3.3.3.6 by.

specifying which post accident monitoring instrumentation readouts are supplimented with recorders. In addition, the change would modify the

" minimum- channels operable" .for the Power Range Neutron Flux instrumen-tation as listed in Table 3.3-10 to correspond with Babcock and Wilcox .

plant Standard Technical Specifications. The Reactor Coolant Total Flow Measurement Range shown in Table 3.3-10 was also changed.

Reason for Proposed Change The clarification of Technical Specification 3.3.3.6 provides a more precise statement of the Post-Accident Instrumentation Limiting Condi-tion for Operation. This will eliminate possible differences in inter-pretation. The modification in Table 3.3-10 would bring CR-3's Techni-cal Specification more in line with B&W Standard Technical Specifica-tions. The Reactor Coolant Total Flow Measurement Range was changed from "110% full fl ow" to the actual installed measurement range of 0-160 X 106 l b/h r.

Safety Evaluation Pursuant the requirements of NUREG-0578, Items 2.1.1, 2.1.3.a , 2.1.3.b, and 2.1.7.b, additional post-accident monitoring' instrumentation was in-stalled at Crystal River Unit 3. While the addition of these accident monitoring instruments was reflected in a Technical Specification change to Table 3.3-10, a necessary corresponding change to the related Techni-cal Specification 3.3.3.6 was overlooked. This change addresses .that oversight. The Reactor Coolant Total Flow Measurement Range was changed to more meaningful units from an operational standpoint.

It is concluded that this change will not adversely affect plant safety.

and does not involve an unreviewed safety question.

ChgRequest(71)D1114-3 P DR h jK50 sigopg 05o0030p PDR

IflSTRUMErlTATION

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POST-ACCIDENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The post accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE with readouts on all channels in the control room. Recorders on instruments 1 through 10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-10, either restore the inopera-ble channel to P3rRABLE status within 30 days, or be in HOT SHUTD0'.iN within the isxt 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.6 Each post-accident monitoring instruaentation channel shall be demonstrated OPERABLE by performance of the CHANf>EL CHECK and CHAN!iEL CALIBRATIO!! operations at the frequacies shown in Tabl e 4.3-7.

CRYSTAL RIVER - UNIT 3 3/4 3-37 Instr (Post Acc)Dil-114-3

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- . _ _ _ _ . . - . . _ - . _ . . _ ._ -_..~._. _ ._ _ _ _ _ _ . . _ . _ _ . _ . . . _ _ _ _ - _, - __

) TABLE 3.3-10 l-POST-ACCIDENT MONITORING INSTRUMENTATION i MINIMUli l MEASUREMENT CHANNELS I INSTRUMENT RANGE OPERABLE

1. Power Range Nuclear. Flux 0 - 125% 1

2. Reactor Building Pressure 0 - 70 psia 2

3. Source Range Nuclear Flux 10-1 to 106 cps 2 1

4. Reactor Coolant Outlet Temperature 5200F - 6200F 2 per loop:

5. Reactor Coolant Total Flow 0 - 160 X 106 lb./hr. -1

(

l 6. . RC Loop Pressure 0 - 2500 psig 2 l 0 - 600 psig 1 l 1700 - 2500 psig 2 l N A 7. Pressurizer Level 0 - 320 inches 2-1 k 8. Steam Generator Outlet Pressure 0 - 1200 psig 2/ steam generator

9. Steam Generator Operating Range Level 0 - 100% 2/ steam generator n 10. Borated Water Storage Tank Level 0 - 50 feet 2 l :>-

5; 11.

Startup. Feedwater Flow. 0 - 1.5 X 106 lb/hr. '2

s

' 12.-Reactor Coolant System Subcooling Margin Monitor' -6580F to +6680F 1 l 5 . . .

E 13. PORV Position Indicator-(Primary Detector) N/A 1

.x I  ;;p 14. PORV Position Indicator (Ba'cku'p. Detector) . N/A 0 l M i E -15. PORY Block Valve Position Indicator N/A 0-u

16. Safety Valve Position. Indicator (Primary Detector). N/A' '1/ Valve.

f' 17. ' Safety Valve ^ Position' Indicator (Backup Detector) N/A' 0-l Ta ble(3.3-10)DN114 p .

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