ML20073R705

Proposed Changes to Tech Spec Revising Section 4.8.1.2, Tables 4.3-11 & 3.6-2 Re Surveillance Requirements for Automatic Load Sequencer & Monthly Testing of Auxiliary Feedwater Sys Logic

ML20073R705
Person / Time
Site:	Davis Besse
Issue date:	05/03/1983
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20073R689	List: ML20073R688 ML20073R695 ML20073R705
References
TAC-46677, TAC-51791, TAC-51792, NUDOCS 8305040503
Download: ML20073R705 (8)

Text

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o ELECTRICAL POWER SYSTEMS SHUTDOWN 4

LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall

be OPERABLE

a. One circuit between the offsite transmission network and the onsite Class 1E distribution system consisting of;

l. One OPERABLE 345 KV transmission line,

2. One OPERABLE 345 KV - 13.8 KV startup transformer, and.

j

3. One OPERABLE 13.8 KV bus, and

b. One diesel generator with:

4

1. Day fuel tank containing a minimum volume of 4000 gallons

.- of fuel, i

2. A fuel storage system containing a minimum volume of 32,000 gallons of fuel, and

3. A fuel transfer pump.

APPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above minimum required A.C. electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until the minimum required A.C. electrical power sources are restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS I 4.8.1.2 The above required A.C. electrical power sources shall be j demonstrated OPERABLE by the performance of each of the Surveillance j Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2.a . 5 A ND 4. 8. l. l. P_ . d. 7.

8305040503 830502 PDR ADOCK 05000346 P pm

! ll DAVIS-BESSE, UNIT 1 3/4 8-5

Docket No. 50-346 License No. NPF-3 Serial No. 938 May 2, 1983 Attachment II

1. Changes to Davis-Besse Nuclear Power Station Unit 1, Appendix A Technical Specifications Table 4.3-11.

A. Time required to Implement. This change is to be effective upon NRC approval.

B. Reason for Change (Facility Change Request 83-050).

In response to NRC request (Log No. 1184) and committed to by Toledo Edison letter dated March 11, 1983 (Serial No. 895).

The output relay contacts in the valve control circuit are not now tested on a monthly basis, but will be incorporated into the monthly channel functional test. Therefore, an amendment request is not required on the output relay contacts as they will be covered under the present Technical Specifications.

C. Safety Evaluation (See attached) 1 l

SAFETY EVALUATION This amendment request changes the Technical Specification surveillance test requirements section 4.3.2.2.1, Table 4.3-11, the channel functional testing of the Auxiliary Feedwater (AFW) system's automatic actuation logic and manual initiation circuit so that it adequately ensures the system's functional capability to its design standard.

The safety function of the AFW system is to provide feedwater to the steam generators for the removal of reactor decay heat in the absence of main feedwater and to promote natural circulation of the reactor coolant system in the event of a loss of all four reactor coolant pumps. The safety function of the Steam and Feedwater Rupture Control System (SFRCS) is to isolate both steam generators automatically (close the main feedwater valves and main steam line valves and trip the turbine) and start the AFW system upon main steam line or feedwater line rupture or loss of all feedwater. SFRCS also initiates AFW system upon loss of all four RCS pumps.

NUREG-0737, Item II.E.1.2. recommends monthly testing of the AFW system's automatic actuation logic and manual initiation circuits (SFRCS). At present, a monthly channel functional test is performed on SFRCS in compliance with NUREG-0737, except the manual actuation buttons are not tested monthly. The reason these buttons are not tested on a monthly basis is that if they were actuated, they would cause a full trip of one channel of SFRCS, which could cause the secondary side of both steam generators to be isolated and one AFW pump would be started.

In Davis-Besse Unit No. 1 SFRCS, all the instrument modules downstream of the manual initiation button are shared with the automatic initiation channels and these modules are required to be functionally tested monthly by Technical Specification Table 4.3-11 item 1, a, b, c and d.

Therefore, the proposed change does not affect the current practice of performing the channel functional tests. No change in the existing test procedures is required.

Therefore, it is concluded that the proposed change is not an unreviewed safety question.

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. TABLE 4.3-11 l-R

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STEAM AND FEEDWATER RUPTURE

• CONTROL SYSTEM f,

INSTRUMENTATION SURVEILLANCE REQUIREMENTS

- C g .

CHAMEL E CHANNEL CHAMEL FUNCTIONAL

$ FUNCTIONAL UNIT CHECK CALIBRATION TEST

1. Instrument Channel

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a. Steam Line Pressure - Low 5 R H+

b. Steam Generator Level - Low ^ $ R M

c. Steam Generator - Feedwater S R M Differential Pressure-High

d. Reactor Coolant Pumps-Loss of S R M g 2. Manual Actuation NA N4

/M(1) J m

g .

+The surveillance period for Steam Line Pressure-Low Instrument is extended to 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />.

= September 16, 1982 o

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(1) Manual actuation buttons shall be tested at least once per 18 months during shutdown.

All other circuitry assdciated with manual actuation shall receive a CIIANNEL FUNCTIONAL TEST a t least once per 31 days.

, ~.

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i Docket No. 50-346 License No. NPF-3 Serial No. 938 May 2, 1983 Attachment III I. Changes to Davis-Besse Nuclear Power Station Unit 1, Appendix A Technical Specifications Table 3.6-2.

A. Time required to Implement. This change is to be effective upon NRC approval.

B. Reason for Change (Facility Change Request 83-018).

To cycle the Main Steam Isolation Valves (MSIVs) in Mode 4 when the pipe is full of steam and not prior to entering Mode 4 (no steam in the pipe) which could score the body bore.

C. Safety Evaluation (See attached)

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SAFETY EVALUATION This amendment request for changes to the Technical Specifications surveillance testing requirements for the Main Steam Isolation Valves (MSIVs) Table 3.6-2.

The safety function of the MSIVs is to isolate the steam generator in the event of a main steam line break or a loss of feedwater transient to keep the steam generator available as heat sink for the reactor coolant system.

The current Technical Specifications requires that these MSIVs be operable during Mode 1, 2, 3 and 4 operations with isolation time as specified. This means that, during plant startup, the surveillance testing of the MSIVs has to be performed prior to entering of Mode 4.

Since the reactor, in Mode 4 during startup, is being cooled by the decay heat removal system rather than the steam generator, the operability of MSIVs does not need to be demonstrated until prior to entering Mode 3.

The proposed change would allow valve testing to be performed in Mode 4 operation during plant startup when there is sufficient amount of steam in the main steam line to keep the piston rings wet and to avoid damaging the valve bore. This change is only applicable during plant startup and does not degrade the intended safety function of either the MSIVs or the steam generator.

Therefore, it is concluded that the proposed change is not an unreviewed safety question.

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+ TABLE 3.6-2 I

l C0iTAlliMEfiT ISOLATI0fi {ALVES (Continued)

• ISCLATION PENETRATIOff VALVE TIME '

( HUMBER NUMBER FUNCTION (seconas) 10

- 16 RC1719A Containment Vessel Vent Header 10 16 RC17193 Containment Vessel Vent Header 18 i SS598 Steam Generator Secondary Water 10 Sample Line Nomal RCS Makeup Line 10 19 MU33 -

15 T

1 19 f HP2A High Pressure Injection Line 15 3 20 f HP2B High Pressure Injection Line DW5831A Demineralized Water Supply Line 10 g 21 DW5'S31B Demineralized Water Supply Line 10 D 21

,15 22 # HP2D High Pressure Injection Line Containment Spray Line 35 25 CS1531 35

'- 26 CS1530 ,C ontainment Spray Line '

Containment Sump Emergency Recirc 71 i

30 f DHSA Line

d

' 31 f DH93 Containment Sump Emergency Recirc

' . 7

'1

.d Line 10 1

o 32 RC1773A RCS Drain t'o RC Drain Tank i

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10 32 RC1773B RCS Drain to RC Drain Tank 15 37 i FW501 Main Feedwater Line

' 15 38 # FW512 Main Feedwater Line 5

Main Steam Line

[ ** 39 i M5100

• • 39 f ICS11A Main Steam Line 10 l y 10

• Main Steam Line 39 i MS375 I 10

' 39 i MS100-1 Main Steam Line 5

0f M5101 Main Steam Line 10

+*40 f ICS11B Main Steam Line 10 40 i MS394 Main Steam Line 7 10 40 f M510101 Main Steam Line m A 17 timandw nt No. 3

TABLE 3.5-2 .

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~ CONTAINMENT ISOLATION VALVES (Con,tinued)

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ISOLATION PENE7 RATION VALVE NUMBER FUNCTION TIME NUMBER 49 DH57 Refueling Canal Fill Line N/A  ;

49 DHS8 Refueling Canal Fill Line N/A l 50 ! HF48 High Pressure Injection N/A 52 MU242 RCP Seal Water Supply N/A 53 MU243 RCP Seal Water Supply N/A 54 MU2t4 RCP Seal Water Supply N/A 55 MU245 RC? Seal Water'. Supply N/A e57 ! MS603 Steam Generator Drain Line N/A 57 i MS603A Steam Generator Drain Line N/A

+58 f W,.5611 Steam Generator Drain Line N/A

-58 ! KS611 A Steam Generator Drain Line N/A 59 Fl ang e . Secondary Side Cleaning (Inside Containment) N/A 5: Fl ange Secondary Side Cleaning (Outside '

Containment) N/A .

67 CV209 Hydrogen Dilution System Supply N/A s Hydrogen Dilution System Supply N/A 69 CY210 71A ! CV20005 Containment Pressure Sensor N/A 71C CF15 Core F1 cod Tank Hitrogen Fill Line -

N/A 72A ! CV20015 Containment Pressure Sensor ,

N/A 72C ! CV6245 Containment Pressure Differential

(

Transmitter N/A N/A 73A ! CV20025 Containment Pressure Sensor 73C ! CV6453 Containment Pressure Differential Transmitter N/A 74A ! CV20035 Containment Pressure Sensor - N/A

'74C DH2735 Pressuriter Auxiliary Spray N/A

'74C DHZ736 Pressuri:er Auxiliary Spray N/A

'May be opened on an intermittent basis under acministrative control.

!Not subject to Type C leak 29e tests. .

! ** Surveillance testing not rec.uired prior to entering MODE 4 but s_

- shall be performed prior to entering Mode 3.

!! Provisions of Specification 3.0.4 are not applicable provided the valve is in the closed positions and deactivated.

l DAVIS-BESSE, UNIT 1 3/4 6-22 Amendment No. ,2', 31 l,

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