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Proposed Tech Specs 3/4.4.4 & 3.4.9.3 Re Relief Valves & Overpressure Protection Sys,Respectively
	ML20073P925
Person / Time
Site:	Wolf Creek
Issue date:	05/14/1991
From:	; WOLF CREEK NUCLEAR OPERATING CORP.
To:	;
Shared Package
ML20073P924	List: ML20073P922; ML20073P925;
References
	NUDOCS 9105240180
	Download: ML20073P925 (9)
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Atthclunent IV to ET 91-0075

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Page 1 of 9 ATTACIMENT IV PROPOSED TECIINICAL SPECIFICATION CilANGES l

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Att,achment IV to LT 91-0075 Page 2 of.9 REACTOR COOLANT SYSTEM 3/4.4.4 REllEf VALVES LIMITING COND1110N FOR OPERA 110N

< 4-A4(P-Maer4perated-ce44efwelves--(+0RVir)-end-the4e-eswe4eted-tdeel ihsert'A3 a >es shall be OPERABLE.

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APPLIC MLITY:

MODES 1, 2, and 3.*

ACTION:

a.

With on Aor more PORV(s) inoperable because of excess)te seat leakage, within 1 haur either restore the PORV(s) to OPERABW status or close the associat block valve (s); otherwise, be in,ai' least HOT STANDBY within the nex hours and in COLD SHUTDOWN tthin the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , b.

With one PORV inoperab ( due to causes ther than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months e Rher restop the PORV to OPERABLE status, or close the associated blot val 6 and remove power from the block valve; restore the PORV to OP LE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STAND in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the follo tig 30 h s.

c.

With both PORV(s) in erable due to cau other than excessive seat leakage, within 1 ur either restore each f the PORV(s) to OPERABLE status or close ieir associated block valve and remove power from the block val >(s) and be in HOT STANDBY within he next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTD 4 within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , d.

With e or more block valve (s) inoperable, within I ho (1) restore th lock valve (s) to OPERABLE status, or close the block alve(s) and

' move power from the block valve (s), or close the PORV and move power from its associated solenoid valve; and (2) apply ACTION -

or

c. above, as appropriate, for the isolated PORV(s),

c.

The-fwevis4onc of Specificat4en 1. 0. A are-not,-app 44sabl e.

SURVEILLANCE REQUIREMENTS L{Atkt Insert tft-to-14+-requ4++ments-of--Spec 444 cat 4ca-AMr 64ch POW

' a ".1 rated OPERABLE at least once per 18 months by ppraance'oT a-

, hall e

CHANNEL CAllBRATIO.

o.4.4.2 Each block valve shall cAemons

. OPERABLE at least once per 52 days by operatin ve through one complete f full travel unless the s closed with power removed in order to meet firements Wp04-ta--or-c.- in Spst i f i c a t i on 3_ a _ a

Wi th 244-RC4-eo14-4eg-tempeeatww-ebove 358".

WOLF CREEK - UNIT 1 3/4 4-10

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Attachment IV to ET 91-0075 Page 3 of 9 Insert A 3.4.4 Both power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLI CAP 11.17Y i MODES 1, 2. and 3.*

ACTION:

a.

With one or both PORVs inoperable because of excessive seat

leakage, within i hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s) with power maintained to the block valve (s); otherwise, be in at least 1107 STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With one PORV inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valves restore the PORV to OPERABLE status within the following 72 hourn or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With both PORVs inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore at least one PORV to OPERABLE status or close its associated block valve and remove. power from the block valve and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and i

in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d.

With one or both block valves inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the block valve (s) to OPERABLE status or place its associated PORV(s) in manual control.

Restore at-least one block valve to OPERABLE status within the next hour if both block valves are inoperable:

restore any remaining inoperable block ~ valve to OPERABLE status within 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s:

otherwise, be-in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , i.

e.

The provisions of Specification 3.0.4 are not applicable.

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With all RCS cold leg temperatures above 368"F.

Insert B l

4.4.4.1 In addition to the requirements'of Specification 4.0.5, each PORV l

shall be demonstrated OPERABLE at least once per 18 months by performing a CHANNEL CALIBRATION of the actuation instrumentation.

4.4.4.2 Each block-valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel'unless the block valve is closed in ordts to meet the requirements of ACTION b.

cr c.

In Specification 3.4.4.

A'ttachment IV to E1 91-0076 Page 4 of 9 REACTOR COOLANT SYSTEM 0JERPRESSURE PROTECTION SYSTIMS LIM 111NG COND1110N FOR OPERA 110N Onsertt

. +9-3-Atlf eemone-of-the-foHowhm-Oveneenm4*tw4k Sp t em &!'.

ye PERABLE:

a.

Two residual heat removal (RHR) suction relief valves each wi h a

<ctpoint of 450 psig i 3%, or b.

Two ower-operated relief valves (PORVs) with Setpoin which do no exceed the limit established in figure 3.4 4 or c.

The Reacto. Coolant System (RCS) depressurized v th an RCS vent of greater than r equal to 2 square inches.

I iPPLICABILITY:

MODE 3 when he temperature of any sCS cold leg is less than ar equal to 368'F MODES 4 an 5, and MODE 6 witYthe reactor vessel head on.

4CT10N:

a.

With one PORV and one RHR su relief valve inoperable, either restoretwoPORVsortwoRfP s tion relief valves to OPERABLE statu within 7 days or depresspfize an

'ent the RCS through at least a 2 square inch vent witrfn the next

hours, b.

With both PORVs a both RHR suction re ' f valves inoperable, depressurize an vent the RCS through at st a 2 square inch vent within 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c.

In the nt the PORVs, or the RHR suction relie alves, or the RCS vent (

are used to mitigate an RCS pressure transi t, a Special Repqr shall be prepared and submitted to the Commiss n pursuant to 5 cification 6.9.2 within 30 days.

The report shall de ribe the ircumstances initiating the transient, the effect of the RVs or-the RHR suction relief valves, or RCS vent (s) on the transie and any corrective action necessary to prevent recurrence.

d.

The prevbien; cf-Specification 3.0.4 are act appMcsbh.

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Attachment IV to ET 91 0075 Page 5 of 9-1 Insert C 3.4.9.3 At icast. one of the following groups of two overpressure protection devices shall be OPERABLE when the Reactor Coolant System (RCS) is not depressurized through a 2 square inch or larger vents a.

Two resioual heat removal (RHR) suction relief valves with Setpoints of 450 psig 1 31 or b.

Two power. operated relief valves (PORV) with Setpoints which do not exceed the limit established in Figure 3.4 4 or c.

One RHR suction relief valve and one PORV with Sotpoints as prescribed above.

APPLICABILITY:

MODE 3 when the temperature of any RCS cold leg is less than or equal-to 368 F.

MODE 4, MODE 5, and MODE 6 when the head is on the Reactor Vessel.

ACTIONi a.

With 'one of the two required overpressure protection devices inoperable in MODE 3 or 4, restore two overpressure protection devices to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 2 square inch vent within the next 8

-hours.

b.

With one of the two required overpressure protection devices inoperable in MODES 5 or 6 restore two overpressure protection devices to OPERABLE status within 24 hot *9, or complete depressurization and venting of the RCS through a least e 2 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c, With both of the two required overpreter

< ea' ion devices inoperable, complete depressurization-and of the RCS through at least a 2 square inch vent within 8 ho-d-

In the event either the PORVs, or the RHR suction relief valves, or the RCS vent (s) are used to mitigate an RCS pressure trausient, a

Special Report shall be prepared and submitted to the Commission pursuant to-Specification 6.9.2 within 30 days, The report shall describe the circumstances initiating the transient, the effect of the PORVs, or the RHR suction relief valves, or RCS vent (s) on the

transient, and any-corrective action necessary to prevent

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recurrence.

e.

The provisions of Specification 3.0.4 are not applicable.

4ttachment IV to ET 91-0075 Page 6 of 9 REACTOR COOLANT SYSifM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a.

Performance of an ANALOG CHANNEL OPERATIONAt TEST on the PORY 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 PORY is required i

OPERABLE; b.

Performance of a CHANNEL CAtlBRATION 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 as follows:

a.

For RHR suction relf1f valve 8708B:

1)

By verifying at least once per 31 days that RHR RCS Suction Isolation Valve (RRSIV) 8701B is open with power to the valve operator removed, and 2)

By verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that RRSIV 8702B is operi.

b.

For RHR suction relief valve 8708A:

1)

By verifying at least once per 31 days that RRSIV 8702A is open with power to the valve operator removed, and, 2)

By verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that RRSIV 8701A is open, c.

Testing pursuant to Specification 4.0.5.

4.4.9.3.3 -The IICS vent-(t)-she41 be vei4Hed-tc-be open-et-4eest once pc r 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when-%e-vent-(s) is be+ng-e4for overprestttre-proteet-ion.

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het when--he-vent-pathay4s-pr-ov44ed-wiu-a--valv e wh ich-44-loc k ed, s e a ! ed, cr cthcnei',e seeueed-4n-the-open-position -then-ver4fy-these-valvec epen at r

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9 Attaciunent IV to ET 91 0075 Page 7 of 9 Insert D With the RCS vented. verify the vent pathway at least once per 31 days when the pathway is provided by a valve (s) that is locked.

sealed.

or othe wise pecured in the open positions otherwise. verify the vent pathway every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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Attachment IV to ET 91 0075 Page 8 of 9-3/4.4 REACTOR COOLANT SYST[H BASES SAFETY VALVES (Continued)

During operation, all pressurizer Code safety valves must be OPERABLE to prevent the RCS from being pressurized above its Safety Limit of 2735 psig.

The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss-of-load assuming no Reactor trip and also assuming no operation of the power-operated relief valves or steam dump valves.

Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler-and Pressure Code.

l 3/4.4.3 PRESSURIZER The 12-hour periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation.

The maximum water volume also e sures that a steam bubble is formed and thus the RCS is not a hydraulically solid system.

The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability of the plant to control Reactor Coolant System pressure and establish natural circulation.

3/4.4.4 RELIEF VALVES I

The power-operated relief valves (PORVs) and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump.

Operation of the PORVs minimizes the undesirable opening of the spring-loaded pressurizer code safety valves.

Each PORV has a remotely operated block valve to provide a positive shutoff capabilit should a relief valve become inoperable.

(insert _L 1

3/4.4.T TEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be main-tained.

The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.

Int.ervice inspection of steam generator tubing is essential in order to maintain surveil-lance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to-corrosion.

Inservice inspection-of steam generator tubing also provides a means of characterizing the nature I

and cause of any tube degradation so that corrective measures can be taken.

1 WOLF CREEK - UNIT 1 B 3/4 4-2 b S" '

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Attachment IV to ET 91 0075 Page 9 of 9 Insert E The PORVs are equipped with automatic actuation circuitry and manual control capability.

Because no credit for automatic PORY operation is taken in the USAR analyses for MODE 1 2 and 3 transients, the p0RVs are considered OPERABLE in either the manual or automatic mode.

The automatic mode is the preferred configuration, as this provides pressure relieving capab111ty without reliance on operator action.

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ML20073P925

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