ML20205S625

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Proposed Tech Specs Table 3.3-3,clarifying Auxiliary Feedwater Actuation Upon Trip of Both Main Feedwater Pumps Re Blocking of Start Signal During Normal Plant Startups & Shutdowns
ML20205S625
Person / Time
Site: Callaway Ameren icon.png
Issue date: 03/27/1987
From:
UNION ELECTRIC CO.
To:
Shared Package
ML20205S603 List:
References
ULNRC-1476, NUDOCS 8704070074
Download: ML20205S625 (8)
v • d • e


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ULNRC- 14 76 Attachment 1-PROPOSED TECHNICAL' SPECIFICATION' CHANGES 8704070074 870327 PDR ADOCK 05000483 P PDR l

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IABLE 3.3-3 (Crntinu d)

['p ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

? .;

, g, MINIMUM t

s j.

TOTAL NO.

CHANNELS CHANNELS APPLICA8tE '

[  % FUNCTIONAL UNIT OF CHANNELS TO TRIP DPERABLE M00E5

  • ACTION [

c 6. Auxiliary Feedwater (Conti'nued)

{ d. Steam Generator Water Level-Low-Low (Continued) it

2) Start Turbine- {

I Driven Pump 4/sta gen. 2/sta. gen. 3/sta gen.

i 1, 2, 3 19*

in any in each 2 operating operating sim. gen.

sim. gen. ,

e. Safety Injection j .

Start Motor-Driven Pumps 'See Item 1. above for all Safety Injection initiating functions and I

4 requirements. {I-4

f. Loss-of-Of fsite Power- ~

{ 5 tart Turbine-Oriven Pump 2 1 2 1, 2, 3

.22 3

i Y g. Trip of All Mah, M Feedwater Pumps - f Start Motor-Oriven Pumps 4-(2/ pump)** 2-(1/ pump 3 1, 2 ### 19 in same *.

separation)

h. Auxiliary Feed- D l-water Pump Suction b Pressure-Low j (Transfer to E5W)
7. Automatic Switchover to 3 2 2 1,2,3 15*

k} ! b I Containment Sump gy, g f.

a. Automatic Actuation
  • 2 ~ s  ;

j Logic and Actuation 1 2 1,2,3,4 14 (4 J '

Relays (55PS) 8 y n b.

g 4 t g

RWST Level - Low-Low 4 2 3 .

1, 2, 3, 4 16 Coincident With M 4T i Safety injection a See Item 1. above for Safety injection initiating functions and -

a requirements. i i

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, REVISION 1 TABLE 3.3-3 (Continued) m, TABLE NOTATION . , ,

  1. Trip f unction may be blocked in this MODE below the P-11 (Pressurizer
  • h' Pressure Interlock) Setpoint.
    1. Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked. .

H* ZNMRT A '

  • lhe provisions of Specification 3.0.4 are not applicable.

""One in Separation Group 1 and one in Separation Group 4 ,

ACTION STATEMENTS ACTION 14.- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE. .

ACTION 15 - With the number of OPERA'BLE channels one less than the Total Number of Channels, operation may proceed until performance of ,

the next required ANALOG CHANNEL OPERATIONAL TEST provided the '.

inoperable channel is placed in the tripped condition within i U

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I hour. . [,

V:

ACTION LG - With the number of OPERABLE channels one less than the Total '

Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum i Channels OPERABLE requirement is set. One additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per b};

Specification 4.3.2.1. ,

ACil0N 17 - With less than the Minimum Channels OPERABLE requirement,  !

operation may continue provided the containment purge supply  ;-

and exhaust valves are maintained closed. ,

AC110N 18 - With the number of OPERABLE channels one less than the Minimum  !.I Channels OPERABLE requirement, restore the inoperable channel l Lo OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANOBY ,

within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hourt,. -

1<

ACTION 19 - With the number of OPERABLE channels one less than the Total

  • i:

N' umber of Channels, STARTUP and/or POWER OPERATION may proceed ..,

provided the following conditions are satisfied: [

a. The inoperable channel is placed in the tripped condition within i hour, and .l

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1 -

f CAllAWAY - UNIT I 3/4 3-20 "

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.- .j . - - -, ., . . - . . . . ...

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ULNRC- 14 76 Attachment 1-INSERT A Trip function may be blocked just before shutdown of the last operating main feedwater pump and restored just after the first main feedwater pump is put into service (following.its startup trip test).

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. ULNRC 1476 Attachment 2 SAFETY EVALUA,TI,OJ{

This amendment application requests that the applicable modes for Item 6.g of Technical Specification Table 3.3-3 be clarified regarding the blocking of auxiliary feedwater (AFW) start signals during normal plant startups and shutdowns. A note would be added to clarify the use of switches in mode 2 that block the automatic signal which starts the motor-driven auxiliary feedwater pumps (A and B) upon the trip of both main feedwater pumps. This note would allow the blocking of this signal just before shutdown of the last operating main feedwater pump during plant shutdowns and would require the restoration of this function just after the first main feedwater pump is placed into service during plant startups. This change would not affect the other AFW start signals (i.e., safety injection signal, loss of offsite power, low-low level in 2 out of 4 channels in any one steam generator) which will be operable at all times during their applicable modes, as given by Table 3.3-3, and available to respond to accident situations.

This amendment application would render the Technical Specifications consistent with NUREG-0830, SER related to the operation of Callaway Plant, and with the FSAR. Section 7.3.2.7 of the former notes that the signal to initiate AFW when the main feedwater pumps are tripped is considered to be an " anticipatory signal" for which no credit is taken in the accident analyses.

In the accident analyses for Cycle 2 (and future cycles), AFW is assumed to be actuated by the low-low steam generator water level signal. Further, the SER states that " bloc <ing will be permitted just before shutdown of the last operating main feedwater pump and removed just after the first main feedwater pump is put into service." The SER concludes that, with bypass indication of the block and operating procedures that appropriately constrain the use of the block switches, the design is acceptable. FSAR Section 7.3.6.1.1.a is consistent with the SER, as follows:

" Manual block of the main feed pump trip signals is provided at the main control board, and is indicated on the ESFAS status panel. This block permits startup and shutdown of the plant without automatic start of the AFPs, while allowing the AFPs to remain available to respond to a demand from any other source."

Since this amendment application does not affect any assumptions made in the safety analyses (i.e., no effect on low-low S/G level signals) nor does it change any of the licensing (

bases for the plant (i.e., SER and FSAR), the change discussed herein would not adversely affect or endanger the health of the general public and does not involve an unreviewed safety question. ,

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~ ULNRC- 14 76 Attachment 3 SIGNIFICANT HAZARDS CONSIDERATIONS This amendment application requests that the applicable modes for Item 6.g of Technical Specification Table 3.3-3 be clarified regarding the blocking, during normal plant startups and shutdowns, of auxiliary feedwater (AFW) start signals which are automatically generated upon the trip of both main feedwater pumps. This clarification would be in the form of a note that would allow the blocking of this start signal to the motor-driven AFW pumps just before shutdown of the last operating main feedwater pump during plant shutdowns and would require the restoration of this function just after the first main feedwater pump is placed into service during plant startups. The following discussions address significant hazards evaluations associated with this change.

This change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

No credit is taken for this start signal in the accident analyses which assume that AFN actuation is generated by the low-low steam generator water level signal. This change has no effect on this or other start signals (i.e., safety injection signal, loss of offsite power) which remain available to respond to accident situations. The use of the block switches precludes the undesired ESF actuation during plant startups and shutdowns under conditions where the motor-driven startup feedwater pump provides the necessary feedwater source.

This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. This is based on the fact that the method and manner of plant operation is being clarified to achieve consistency with those documents establishing the licensing bases for Callaway Plant (i.e., NUREG-0830, SER related to the operation of Callaway Plant, Section 7.3.2.7 and FSAR Sections 7.3.6.1.1.a, 15.2.6, and 15.2.7).

This change does not involve a significant reduction in a margin of safety. This is based on the fact that no design changes are involved and the change to clarify mode applicability ,

is consistent with NRC's safety evaluation of the auxiliary l feedwater system actuation design. j The Commission has provided guidance concerning the application of the standards in 10CFR50.92 by providing certain examples (48FR14870). This change request is similar to the example of a change involving no significant hazards which relates to a change that is administrative in nature. The change

t ULNRC-14 76 4 - Attachmsnt 3 provides-consistency between the Technical Specifications and the Safety Evaluation Report (NUREG-0830) and'the FSAR. As such, the requested amendment.does not present a significant. hazard.

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4 ULNRC- 14 76 Attachment 4 4

Application Fee CHECX NUMBER 80 0245 m

UNION ELECTluC COMPANY sr.ums.wssoum 219756 10 ceNicaat eANx or xtNNeTr. uissouai 4591 oa'r ^"aa' PAY .

$ ** * * ** 150 00 U S NUCLEAR REGULATORY 03 24 87 TO THE ORDER OF CDMMISSION l CHECK $ OVER Isiset REQUIRE COUNTERSIGNATURE l 1717 H ST NW WASHINGTON DC gqA , " ;;.,g. g

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THIS CHECK 20555 h*a ta 4 a  :

VOID AFTER h '$,\iihlh5}thMvirdu f AufMOAtZ13 $4NAlUAE 90 DAYS .

co attas*aaruas n'2L97SE2n* l'OB L 50 24 59t* 84 035 & n' L.

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