ML17292A942

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Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs
ML17292A942
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 07/16/1997
From:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17292A941 List:
References
NUDOCS 9707230292
Download: ML17292A942 (22)
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Text

RCS P/T Limits 3.4.11 ACTIONS continued CONDITION REQUIRED ACTION ,COMPLETION TIME C ---------NOTE----'----- C.1 Initiate action to Immedi ately Required Action C.2 restore parameter(s) 1 shall be completed if to within limits.

this Condition is entered. ~ND C.2 Determine RCS is Prior to Requirements of the acceptable for entering MODE 2 LCO not met in other operation. or 3 than MODES 1, 2, and 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 -NOTE-Only required to be performed during RCS heatup and cooldown operations, and RCS inservice leak and hydrostatic testing.

Verify: 30 minutes

a. RCS pressure and RCS temperature are within the applicable limits specified in Figures 3.4.11-1, 3.4.11-2, -and-3.4.11 3g 3.q,l<-9 nh ~,S,<i-S
b. RCS heatup and cooldown rates are a 100'F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period; and C. RCS temperature change during inservice leak and hydrostatic testing is c 20'F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period when the RCS pressure and RCS temperature are not within the limits of Figure 3.4.11 g,~ S,q, tl-'E.

3 (continued)

NNP-2 3.4-24 Amendment No. 149 9707230292 9707i6 PDR ADOCK 050003'P7 P PDR

RCS P/T Limits 3.4.11 1400 1300 1200 1100 1000

~ ~ (185', 1 035 ps lg) soo 800 0

700 600 (110', 638 pslg) o 600 4oo 0

300 (110', 312 pslg) 200 (80', 312 pslg) 100 0

0 60 100 'l60 200 250 300 350 400 450 600 Reactor Metal Temperature (Core Beltline, 'F) 850657 21 Jan 1WT Figure 3.4.11-1$ (Page of g Inservice Leak and Hydrostatic Testing Curve for 12EFPY WNP-2 3.4-28 L ~ ~

RCS P/T Limits 3.4.11

't400 1300 1200 4100 co 1000 900 6', 1035 psfg) 800 O

7oo O

600 500 400 (010', 452 psfg) 300 (110', 312 psfg) 200

'300 (80', 312 psig) 0 0 50 'joo 150 200 250 300 350 400 450 500 Reactor Metal Temperature (Core Seltline, F) aact67.1 Hw 1NO p

Figure 3.4.11-f (Page 1 of 1)

Inservice Leak and Hydrostatic Testing Curve Fot. 32 E.FY MNP-2 3.4-gat Amendment No. 149

RCS P/T Limits 3.4.11

.1400 1300 1200 1100 1000 (23 7oF 1 035 ps ig) goo 800 0

700 0

600 o 500 400 Q.

(140', 412 psig) 300 (140', 312 psig) 200 (80', 312 psig) 100 0 50 100 150 200 250 300 350 400 450 500 Reactor Metal Temperature (Core Beltline, 'F) 050657A Jan 1897 Figure 3.4.11-pa (Page K of @

Non-Nuclear Heating and Cooldown Curve for 12 EFPY

)

WNP-2 3. 4-~9a -Revision-0

t RCS P/T Limits 3.4.11 1400 1300 1200

~

eP 1100 L, 1000

~s F, 10 35 psig) 900 x

a 800 0

I 700 (255'140',

600 500 400 362 ps')

a- 300 (140', 312 pslg) 200 (110', 342 pslg)

I t 100 (8 F28 t )

0 0 60 100 150 200 260 300 350 400 450 500 Reactor Metal Temperature (Core Beltline, 'Fj "t

Figure 3.4-11-g (Page 1 of I)

Non-Nuclear Heating and Cooldown Curve For 32 WNP-2 3.4-g4 ( Amendment No. 149

RCS P/T Limits 3.4.11 1400

'1300 1200

'! 000 900 (295', 1035 pslg) 800 0

700 600 500 400 CL (180', 362 pslg)

I I I 300 (180', 312 pslg)

I I 200 (140', 312 pslg)

I I (100', 281 pslg) 80', 233 pslg) 0 50 100 150 200 250 300 350 400 450 500 Reactor Metal Temperature (Core Beltllne, F) 5 Figure 3.4.11-$ tPage 1 of 1)

Nuclear Heating and Cooldown Curve MNP-2 3.C-)d'P Amendment No. 149

v li

ATTACHMENT2 Clean Version of the Technical Specification Pages

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.6.2 'econdary Containment Isolation Instrumentation 3.3-59 3.3.7.1 Control Room Emergency Filtration (CREF) System Instrumentation . . 3.3-63 3.3.8.1 Loss of Power (LOP) Instrumentation 3.3-68 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring 30372 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4-1 3.4.1 Recirculation Loops Operating 3.4-1 3.4.2 Jet Pumps 3.4-5 3.4.3 Safety/Relief Valves (SRVs) w . 25% RTP 3.4-7 3.4.4 Safety/Relief Valves (SRVs) < 25% RTP 3.4-8 3.4.5 RCS Operational LEAKAGE 3.4-10 3.4.6 RCS Pressure Isolation Valve (PIV) Leakage . 3.4-12 3.4.7 RCS Leakage Detection Instrumentation 3.4-14 3.4.8 RCS Specific Activity 3.4-16 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System Hot Shutdown 3.4-18 3.4.10 Residual Heat Removal (RHR) Shutdown Cooling System Cold Shutdown . . . 3.4-21 3.4.11 RCS Pressure and Temperature (P/T) Limits 3.4-23 3.4.12 Reactor Steam Dome Pressure 3.4-33 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5-1 3.5.1 ECCS Operating 3.5-1 3.5.2 ECCS Shutdown . . . 3.5-6 3.5.3 RCIC System 3.5-10 3.6 CONTAINMENT SYSTEMS 3.6-1 3.6.1.1 Primary Containment 3.6-1 3.6.1.2 Primary Containment Air Lock . ... . . . . . . 3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs) . 3.6-8 3.6.1.4 Drywell Air Temperature 3.6-16 3.6.1.5 Residual Heat Removal (RHR) Drywell Spray 3.6-17 3.6.1.6 Reactor Building-to-Suppression Chamber Vacuum Breakers . 3.6-19 3.6.1.7 Suppression Chamber-to-Dryw'ell Vacuum Breakers 3.6-22 3.6.1.8 Main Steam Isolation Valve Leakage Control (MSLC) System . . . . . . . . . . . . . . . 3.6-25 3.6.2.1 Suppression Pool Average Temperature . 3.6-27 3.6.2.2 Suppression Pool Water Level 3.6-30 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3.6-31 continued WNP-2 Amendment No.

RCS P/T Limits 3.4.11 ACTIONS continued CONDITION REQUIRED ACTION COMPLETION TINE C ---------NOTE--------- C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed if to within limits.

this Condition is entered. AND C.2 Determine RCS is Prior to Requirements of the acceptable for entering NODE 2 LCO not met in other operation. or 3 than NODES 1, 2, and 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 -NOTE Only required to be performed during RCS heatup and cooldown operations, and RCS inservice leak and hydrostatic testing.

Verify: 30 minutes a ~ RCS pressure and RCS temperature are within the applicable limits specified in Figures 3.4.11-1, 3.4.11-2, 3.4.11-3, 3.4.11-4, and 3.4.11-5;

b. RCS heatup and cooldown rates are

~ 100'F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period; and

c. RCS temperature change during inservice leak and hydrostatic testing is x 20'F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period when the RCS pressure and RCS temperature are not within the limits of Figure 3.4.11-3 or 3.4.11-4.

(continued)

WNP-2 3.4-24 Amendment No.

RCS P/T Limits 3.4.11 1400 1300 1200 1100 1000 (185', 1035 ps lg) goo x 800 0

700 0

600 (1'l0', 638 pslg) 500 400 CL 300 (110', pslg) 200 31'80',

312 pslg) 100 0 50 100 150 200 250 300 350 400 450 500 Reactor Metal Temperature (Core Beltllne, 'F)

Q506578 Jan 1NT Fi gure 3.4.11-1 (Page 1 of 1)

Inservice Leak and Hydrostatic Testing Curve for 12 EFPY WNP-2 3.4-28 Amendment No.

RCS P/T Limits 3.4.11 1400 1300 1200 1100

'e 1000 lL 900 (226 F,1035 psig) 800 O

700 600 500 400 (440', 452 psig) 300 200 (110', 312 psig)

(80', 342 psig) 100 0 50 100 150 200 250 300 350 400 450 500 Reactor Metal Temperature (Core Beltline, F) 050657.1 Nov 1998 Figure 3.4.11-2 (Page 1 of 1)

Inservice Leak and Hydrostatic Testing Curve for 32 EFPY WNP-2 3.4-29 Amendment No.

RCS P/T Limits 3.4.11 1400 1300 1200 1100 1000 900 (23 7', 1035 pslg) 800 700 600 o 500 400 (1 40', 412 pslg) 300 (140', 312 pslg) 200 (80', 312 pslg) 100 0 50 100 150 200 250 300 350 400 450 500 Reactor Metal Temperature (Core Beltline, F)

Jvl 1997 Figure 3.4.11-3 (Page 1 of 1)

Non-Nuclear Heating and Cooldown Curve for 12 EFPY WNP-2 3.4-30 Amendment No.

RCS P/T Limits 3.4.11 1400 1300 1200

~~

~

1100 L, 1000

~t (255o F,10 35 psig) 900 x

n 800 I-0 700 600 500 400 (140', 362 psig)

a. 300 (140', 312 pslg)

.200 (110', 312 psig)

I I 100 ( F i )

0 50 100 150 200 250 300 350 400 450 500 Reactor Metal Temperature (Core Beltllne, F) 0506574 Nov 100'igure 3.4-11-4 (Page 1 of 1)

Non-Nuclear Heating and Cooldown Curve for. 32 EFPY MNP-2 3.4-31 Amendment No.

RCS P/T Limits 3.4.11 1400 1300 1200 1100 l000 900 (2 95', 1035 p slg) 800 0

700 600 o 500 400 CL (180', 362 pslg)

I I I 300 (180', 312 pslg)

I I 200 (140', 312 pslg)

I I (100 F,281 pslg) 100 80', 233 pslg) 0 50 100 150 200 250 300 350 400 450 500 Reactor Metal Temperature (Core Beltllne, 'F) 95XSTZ Jsn1N7 Figure 3.4.11-5 (Page 1 of 1)

Nuclear Heating and Cooldown Curve WNP-2 3.4-32 Amendment No.

Reac or Steam Dome Pressure 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4. 12 Reactor Steam Dome Pressure LCO 3.4.12 The reactor steam dome pressure shall be a 1035 psig.

k APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor steam dome A.1 Restore reactor steam 15 minutes pressure not within dome pressure to limit. within limit.

B. Required Action and B. 1 Be in MODE 3. 12 hours associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4. 12. 1 Verify reactor steam dome pressure is 12 hours x 1035 psig.

WNP-2 3.4-33 Amendment Nn.

ATTACHMENT3 Planned Technical Specification Bases Changes

RCS P/T Limits B 3.4.11 BASES APPLICABLE the curves and limits required by this Specification. Since SAFETY ANALYSES the P/T limits are not derived from any DBA, there are no (continued) acceptance limits related to the P/T limits. Rather, the P/T limits are acceptance limits themselves since they preclude operation in an unanalyzed condition.

RCS P/T limits satisfy Criterion 2 of Reference 9.

LCO The elements of this LCO are:

RCS pressure and temperature are within the limits specified in Figures 3.4.11-1, 3.4.11-2, and 3.4.11-3 and heatup and cooldown rates are < 100~F in any I hour period during RCS heatup, cooldown, and inservice leak and hydrostatic testing, and the RCS temperature change during inservice leak and ~

hydrostatic testing is < 20'F in any I hour period when the RCS pressure and RCS temperature are not within the limits of Figure 3.4.11-+ 3 cr '5 A ~~ ~j

b. The temperature difference between the reactor vessel bottom head coolant and the reactor 'pressure vessel (RPV) coolant is < 145'F during recirculation pump startup, and during increa'ses in THERMAL POWER or loop flow while operating at low THERMAL POWER or loop flow;
c. The temperature difference between the reactor coolant in the respective recirculation loop and in the reactor vessel is < 50'F during recirculation pump startup, and during increases in THERMAL POWER or loop flow while operating at low THERMAL POWER or loop flow
d. RCS pressure and temperature are within the limits specified in Figure 3.4. 11-P', prior to achieving criticality; and 5
e. The reactor vessel flange and the head flange temperatures are > 80'F when tensioning the reactor vessel head bolting studs.

These limits define allowable operating regions and permit a large number of operating cycles while also providing a wide margin to nonductile failure.

continued WNP-2 B 3.4-55 Revision 5

RCS P/T Limits B 3.4.11 BASES ACTIONS C.l and C.2 (continued)

Operation outside the P/T limits in other than HODES 1, 2, and 3 (including defueled conditions) must be corrected so that the RCPB is returned to a condition that has been verified by LEFH analyses. The Required Action must be initiated without delay and continued until the limits are restored.

Besides restoring the P/T limit parameters to within limits, an evaluation is required to determine if RCS operation is allowed. This evaluation must verify that the RCPB integrity is acceptable and must be completed before .

approaching criticality or heating up to > 200'F. Several methods may be used, including comparison with pre-analyzed transients, new analyses, or inspection of the components.

ASHE Section XI, Appendix E (Ref. 6), may be used to support the evaluation; however, its use is restricted to evaluation of the beltline.

Condition C is modified by a Note requiring Required Action C.2 be completed whenever the Condition is entered.

The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits.

Restoration alone per Required Action C.l is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.

SURVEILLANCE SR 3.4.11.1 RE(UIREHENTS 4 Verification that operation is within limits is required every 30 minutes when RCS pressure and temperature conditions are undergoing planned changes. This Frequency is considered reasonable in view of the control room indication available to monitor RCS status. Also, since temperature rate of change limits are specified in hourly increments, 30 minutes permits assessment and correction of

. minor deviations. The limits of Figures 3.4.11-1, 3.4.11-2,

~d 3.4.11-3 are met when operation is to the right of the applicable 1 mit curves.

It 5 Surveillance for heatup, cooldown, or inservice leakage and hydrostatic testing may be discontinued when the criteria given in the relevant plant procedure for ending the activity are satisfied.

continued MNP-2 B 3.4-58 Revision 5

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