ML20070F622

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Proposed Tech Specs 4.4.9.3.2 & 4.5.2.d Re RHR Suction Valve Autoclosure Interlocks
ML20070F622
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 03/05/1991
From:
WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20070F609 List:
References
ET-91-0036, ET-91-36, NUDOCS 9103080374
Download: ML20070F622 (4)
v • d • e


Text

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Attachm:nt IV to ET 91-0036 Page 1 of 4 ATTACIMENT IV PROPOSED TECHNICAL SPECIFICATION CHANGES I

r 1

i l

t 9103080374 910303 PDR ADOCK 05000482 P PDR

<' - ' Attachment IVLto ET 91-0036 Page 2 of 4 REACTOR COOLANT SYSTEM i SURVEILLANCE REQU1REMENTS 4;4.9.3.1 Each PORV shall be demonstrated OPERABLE t'y: *

a. Performance of an ANALOG-CHANNEL OPERATIONAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days prior to-entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereaf ter when the PORV is. required OPERABLE;
b. Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months; and
c. Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORV is being used for overpressure protection.

4.4.9.3.2 Each RHR suction relief valve shall be demonstrated OPERABLE when the RHR suction relief valves are being used for cold overpressure. protection i as follows:

. a. For RHR suction relief valve 87088:

1) _ Sy ve-ifying at 1:::t once per 31 d:y: th:t " PCS Sectic"

!:01: tier V:lve (P95!V) 8701S it oper "ith power to the calv cperater removed, end 72

2) By verifying at least once per-M-hours that PRS!V 87023
per, +- ==- == ,._.

RHR RCS Suction Isolatlon Valves

b. For RHR suction relief valve 8708A: (RR$1Vs)87018and87028areopen;.
1) Cy veriffing at 1. ::t cue per 31 day; that o95!" 8702? i:

-cpen ith pcwcr to the velve e-ter removed, and

2) By verifying at least once per hours that RRSI ( 8701A M 8702'A) open.

Os

c. Testing pursuant to Specification 4.0.5.

4.4.9.3.3 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

  • when the. vent (s) is being used for overpressure protection.
  • Except when the vent pathway is provided with a valve which is locked, tealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.

WOLF CREEK - UNII 1 3/4 4-35

~ E+ Attachment IVLto ET 91-0036~

Page 31of.4 4

. -EMERGENCY CORE-COOLING SYSTEMS S'URVEILLANCE'REQOIREMENTS 4.5.2.- Each ECCS subsystem shall be demonstrated OPERABLE: ,

-a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves-are'.in the. indicated' positions with power to the valve operators-removed:

Valve Number- Valve function Valve Position BN-HV-8813 Safety Injection to Open

.RWST Isolation Viv EM-HV-8802A(B) . SI Pump Discharge  : Closed Hot Leg Iso.Vivs EM-HV-8835 Safety Injection Open Cold Leg Iso Valve EJ-HV-8840 RHR/SI Hot Leg Closed Recirc Iso Valve EJ-HV-8809A RHR to Accum'Inj Open Loops'1 & 2 Iso Viv EJ-HV-8809B RHR to Accum Inj Open Loops 3 & 4 Iso Viv

.b.- At ieast once per 31 days by:

, ~1) . Verifying that the: ECCS piping is' full of water by venting the ECCS poinp casings and accessible discharge piping high points, and

2) -Verifying that each valve!(manual, power-operat'ed, or automatic) in-the flow path that is~not locked, sealed, or otherwise secured in position, is in its correct position.
By a visual inspection which verifies-that no loose' debris (rags, c.

trash, clothing, etc.)'is present in the containment which could be transported-to the containment sump and cause restriction of'the. .

pump suctions during LOCA conditions. This visual inspection shall

~

-be performed:

1) 'For all accessible areas:of the containment prior to establishingECONTAINMENT INTEGRITY, and
2) Of-the areas-affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established. 1
d. At least;once per 18 months by:

1)- Verifying automatic i:012 tier :nd interlock action of the RHR SystemfromtheReactorCoolantSystembyensuringthat7f )

-ef d fith_ a simulated or actual Reactor Coolant System pressure signal greater than or equal to 425 psig,the interlocks I prevent the valves from being opened f f-e+  !

l b) Nilh O ',imtNated-OP-dC-tt04-8eac4&T C00l0fd. -Sy64:em-fric0 0urc

'ignal Ic;; than or equal to-750 p,ig the 'nterlock:

cause thevolve; to cutentically cl0cc.

WOLF CREEK - UNIT 1 3/4 5-4 a

_ , - . c- . . - - , , _ . _ . _ _ _ ._ .~ , . - . ._ ~ _ . . _ . - - .

. - - - . - . . . - - - . - - - . - - - - . - - . ~ . - - . . . .

1' ? Attachment >lV to ET 91-0036 1

Page 4tof 4 tREACTOR COOLANT SYSTEM BASES PRESSURE / TEMPERATURE LIMITS (Continued)

. _ Following the generation-of pressure-temperature curves for both the steady state and finite heatup rate situations, the final _ limit curves are produced as follows. A composite curve is constructed based on1a point-by-point comparison of the steady-state and finite heatup rate data. . At any given temperature,-the allowable pressure is taken-to be the lesser of the three values.taken from the curves under consideration.

The use of the composite curve is necessary to set conservative heatup . l

' limitations because it is possible for conditions to exist such that over the ccurse of the heatup ramp ;the controlling condition switches from the inside to the outside and the pressure limit must at all times be based on analysis of the most critical. criterion.

Although the pressurizer operates in temperature ranges above those for which there-is reason for concern of nonductile failure, operating limits are provided to assure compatibility of operation with the fatigue analysis performed in accordance with the ASME Code requirements.

The OPERABILITY of two PORVs, or two RHR suction relief valves, or an RCS vent opening of at least 2 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are less than or equal to 368 F.

' Either_ PORV or either RHR suction relief. valve has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to

-either: (1) the start of an idle RCP with the secondary water temperature of

-the steam. generator less then or equal to 50 F above the RCS cold leg tempera-tures,:or (2) the start of a centrifugal charging pump and its injection-into a water solid RCS.

RP9 RCS ;uctier, i;;l; tion valve: S701A chd S are interlocked with er "^"

tr:! wide range pre::ure tran;mitter and valve: 8702A and B-are interlocked with a "S" train wid range prc :ure tran;mitter. Rem 0ving pcwcr ' rem valv0:

S7010 and-6702A, prcycnt ; ; ingle failure frem inedvertently 1:cleting both "99 Ouctier relief valve; while maintaining RHR i:Olation capabi'ity for both R"R flew p th:.

-In addition to opening RCS vents to meet _ the requirement of Specifica-

- tion 3.4.9.3c., it is acceptable to remove a pressurizer Code safety valve,

[ open a.PORV block valve and remove power from the valve operator in conjunction with disassembly of a PORV and removal of its internals, or otherwise open the i - R C S .-

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i WOLF CREEK - UNIT 1 8 3/4 4-13 Amendment No. 40 e

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