ML20236U635

From kanterella
Revision as of 20:08, 19 February 2021 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Proposed Tech Specs Re Mods to Standby Liquid Control Sys Discharge Piping
ML20236U635
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 11/25/1987
From:
SYSTEM ENERGY RESOURCES, INC.
To:
Shared Package
ML20236U634 List:
References
NUDOCS 8712030225
Download: ML20236U635 (2)


Text

- _ _ - _ _ . __

\

Attachment IV INSTRUMENTATION to AECM-87/0209 BASES j

  • ISOLATION ACTUATION INSTRUMENTATION (continued)

D the A.C. power. supply is lost and is restored by startup of the emergency diesel generators. In this event, a time of 10 seconds is assumed before the valve starts to move. In addition to the pipe break, the failure of the' D.C. operated valve is assumed; thus the signal delay (sensor response) is concurrent with l the 10 second diesel startup. The safety analysis considers an allowable  !

inventory loss in each case which in turn determines the valve speed in conjunc- l tion with the 10 second delay. It follows that checking the valve speeds and- l the 10 second time for emergency power establishment will establish the re'sponse '

time for the isolation functions. However, to enhance overall system relia-bility and to monitor instrument channel response time trends, the isolation l actuation instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME. ,

- 1 A Ope' ration with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that.the  ;

difference between each Trip Setpoint and the Allowable Value is equal t'o or greater than the' drift allowance assumed for each trip in the safety analyses.

I 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION The emergency core cooling system actuation instrumentation is provided to initiate actions to mitigate the consequences of accidents that are beyond the ability of the operator to control. This specification provides the OPERABILITY requirements, trip setpoints and response times that will ensure effectiveness of the systems to provide the design protection. Negative barometric pressure 1

. fluctuations are accounted for in the trip setpoints and allowable values  !

specified for drywell pressure-high. Although the instruments art lis".ed by system, in some cases the same instrument may be used to send the actuation signal to sort than one systen at the same time.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or l greater than the drift allowance assumed for each trip in the safety analyses. I 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION

' ]

psys Tea ic pa d ran ien without cram pr id s TVS) cir ulat on p ns f 1 miti g th conse uenc 'of eu ike oc urr ne ip  !

l of fai re to ser d rin an ntic ated ransi nt. he spo eo th i p1 t t s ost la d e ent alls ithin he e velop of tudy eve ts n l rch 71 nd k5 <,

ra El et c omp ny

-4 , te D emb r 19 pic Rep rt NE 10 ,d

,a Sect n 15 App ndix/15A d

F R. j The end-of-cycle recirculation pump trip (EOC-RPT) system 'is a part of 'the Reactor Protection System and is an essential safety supplement to the reactor -

trip. The purpose of the EOC-RPT is to recover the loss of thermal sargin which '

occurs at the end-of cycle. The physical phenomenon involved is that the void I reactivity feedback due to a pressurization transient can add positive reactivity to the reactor system at a faster rate than the control rods add negative scram ,

reactivity. . Each EOC-RPT system trips both recirculation pumos, reducing coolant ' l flow in order to reduce the void collapse in the core during two of the sost limiting pressurization events. The two events for which the EOC-RPT protective GRAND GULF-UNIT 1 B 3/4 3-2 Amendment No. __

kk oh j6 P f

~

' Attachment XV

.. to AECM-87/0209 TABLE 3.6.4-J,(Continued)

, CONTAINMENT AND DRYWELL ISOLATION VALVES SYSTEM AND PENETRATION VALVE NUMBER NUM8ER Orwell (Gentinued)

  • CR0 to itacire. 833-F017A 326(0)

Pump A Seals Instrunent Air F53-F008 335(I)

Standby Liquid C41-F007 328(I)

Control

. Standby Liquid C41-F006 328(0)

Contro) 328(t)

Cont. Cooling P42-F115 329(!)4 54o Cog adQ 4 3v.4 h t tc.f.g c4(-F 218 Water Supply Dryw11 Chilled P72-F147 332(I)

Water Supply Condensate Flush 833-F204 333(I)

Conn. -

Condensate Flush 833-F205 333(0)

Conn. ,

Combustible Gas E61-F002A 339(0)

Control Combustible Gas E61-F002B 338(0)

Contro1 Combustible Gas E61-F004A 340(0)

Control Combustible Gas ~~

E61-F0048 340(0)

Control Upper Containment G41-F265 342(0)

Pool Drain -

CRD to Recire. 833-F013B 346(I)

. Pump B Seals CRD to Recire. 833-F0178 346(0)

' Pump B Seals Service Air P52-F196 363(I)

Cont. Leak Rate M61-F021 438A(I)

Test Inst. -

j Cont. Leak Rata M61-F020 438A(0)

Sys.

' BLIND FLANGES Cont. Laak Rata NA 40(I)(0)

Sys.

Cont. Laak Rate NA 82(I)(0)

Sys.

Containment NA 343(I)(0)

Laak Rate System ,

GRAND GULF-UNIT 1 3/4 6-42 Amend:nent Ho.

W- - _ _ _ - . _ _ _ _ _ _ _ _ _ . _ . - . _ _