ML20148E757

Proposed Tech Specs Pages 3/4 5-5,5-6a & 6-13,revising TS Surveillances 4.5.2.f & 4.6.2.2.b to Replace Pump Differential Pressure Acceptance Criteria W/Pump Acceptance Curve

ML20148E757
Person / Time
Site:	Millstone
Issue date:	05/30/1997
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20148E752	List: B16463, Application for Amend to License NPF-49,by Incorporating Proposed Revision Into TS Surveillances 4.5.2.f & 4.6.2.2.b, to Replace Pump Differential Pressure Acceptance Criteria W/Pump Acceptance Curve ML20148E757
References
NUDOCS 9706030250
Download: ML20148E757 (13)

Text

_ _ _. _. _. _ _.. _. _.._ _ _._ _._ _ _ _. _ _. _ __

i December 28,1995 EMERGENCY CORE COOLING SYSTEMS k-SURVEILLANCE REQUIREMENTS (Continued) 2)

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.

At least once each REFUELING INTERVAL by:

l e.

1 l

1)

Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection actuation test signal, and 1

2)

Verifying that each of the following pumps start au+.omatically l

upon receipt of a Safety injection actuation test signal:

a)

Centrifugal charging pump, b)

Safety Injection pump, and j

c)

RHR pump.

3)

Verifying that the Residual Heat Removal pumps stop automatically upon receipt of a Low-Low RWST Level test signal.

i f.

By verifying that each of the following pumps develops the indicated i

differential pressure on recirculation flow when tested pursuant to Specification 4.0.S:

1)

Centrifugal charging pump 1 2411 psid, 2)

Safety Injection pump 1 1348 psid, i

3)

RHR pump 2 165 psid, and i

accorche 1

4)

Containment recirculation pump h ;;;id.

4/164 Fyre 35-l g.

By verifying the correct position of oath electrical and/or mechanical position stop for the following ECCS wottle valves:

1)

• Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and 2)

At least once each REFUELING INTERVAL.

l ECCS Throttle Valves Valve Number Valve Number

/

\\

3SIH*V6 3SIH*V25 3SIH*V7 3SIH*V27 9706030250 970530 PDR ADOCK 05000423 P

PDR 3/45-5 Apenknt No. ff,124 4

)

c December 28,1995 l

CONTAINMENT SYSTENS i

(

RECIRCULATION SPRAY SY$ TEN l

LINITING CONDITION FOR OPERATION I

3.6.2.2 Two independent Recirculation Spray Systems shall be OPERABLE.

f APPLICABILITY: MODES 1, 2, 3, and 4.

AGT.10ti:

With one Recirculation Spray System inoperable, restore the inoperable system i

to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the l

next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable Recirculation Spray System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 i

hours.

$URVEILLANCE REQUIRENENTS i

4.6.2.2 Each Recirculation Spray System shall be demonstrated OPERABLE:

\\

a.

At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path is not locked, i

sealed, or otherwise secured in position, is in its correct j

positilon; l

B,,, verifying, jjist on_.peireg1114cn flowggg;

.... e rer..... i,reeeere egree.er y._r. er ease......J;Q..:;w: e:

b.

c n

,l mms de tested pursuant to specificatun-9.0.5;

~~

! \\ accep%ce c.

At least once each REFUELING INTERVAL by verifying that on a CDA l

crNNuI<,e<,

i sfuifie test signal, each recirculation. spray pump starts automatically i

p yy 35-l after a 660 120 second delay; i

d.

At least once each REFUELING INTERVAL, by verifying that each l l

automatic valve in the flow path actuates to its correct position on a CDA test signal; and 1

e.

At least once per 10 years by performing an air or smoke flow test l

through each spray header and verifying each spray nozzle is unobstructed.

l l

1 i

I l

1(

MILLSTONE - UNIT 3 3/46-13 Amendment No. PP, JPP,122 t

Docket No. 50-423 B16463 i

1 1

a Millstone Nuclear uwer Station Unit No. 3 r

Proposed Revision to Technical Specification Recirculation Sorav System Surveillances (PTSCR 3-24-97)

Retvoed Paae(s) 1 May 1997

i U.S. Nuclear Rtgulatory Commission

'd16463%ttachment 3\\Page 1 RETYPE OF PROPOSED REVISION Refer to the attached retype of the proposed revision to the Technical Specifications.

The attached retype reflects the currently issued version of the Technical Specifications. Pending Technical Specification revisions or Technical Specification i

2 revisions issued subsequent to this submittal are not reflected in the enclosed retype.

The enclosed retype should be checked for continuity with Technical Specifications prior to issuance.

i I

i I

i i.

1 I

}

=

ENERGENCY CORE C0OLING SYSTEMS SURVEILLANCE REQUIRENENTS (Continued)

J s

4 2)

A visual inspection of the containment sump and verifying that i

the subsystem suction inlets are not restricted by debris and thatthesumpcomponents(trashracks, screens,etc.)showno evidence of structural distress or abnormal corrosion, e.

At least once each REFUELING INTERVAL by:

1)

Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection actuation test signal, and 2)

Verifying that each of the following pumps start automatically f

upon receipt of. a Safety Injection actuation test signal.

a)

Centrifugal charging pump, b)

Safety Injection pump, and i

c)

RHR pump.

3).

Verifying that the Residual Heat Removal pumps stop automatically upon receipt of a low-Low RWST Level test signal.

i f.

By verifying that each of the fo11'owing pumps develops the indicated differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1)

Centrifugal charging pump 2 2411 psid, 2)

Safety Injection pump 1 1348 psid, 3)

RHR pump 1 165 psid, and 4)

Containment recirculation pump in'accordance with Figure 3.5-1.

g.

By verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:

1)

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and 2)

At least once each REFUELING INTERVAL.

ECCS Throttle Valves Valve Number Valve Number 3SIH*V6 3SIH*V25 5

3SIH*V7 3SIH*V27 MILLSTONE - UNIT 3 3/4 5-5 Amendment No. pp, #p, 0521

.z

i

-]

I I,

l e-O w

w u

w o

o o

~

pig!

r;7 s

.l

~

(

l;ic l.jp 7

,.i f_

2_ I

. j

.Iji T

_ I_I,

.l,

~

m

._ lLf_

o e

.l 4

p7_

4.. !pI c

.lyp 1

l

.l4>'

d l._i _ 7,.

. !b..

77I,.

i,g s

o A

8 lL[.

.q;.

f u.

Igi.

s

.~-

l4_ i4j_ I2. i_ ql.

9 v

t ij; 7

I m

.lel.

3.I, L,

Iwi

.lel.

,l1 P

_I i.

a

.l1 v

.!+l

.._lm_ il_

_1,

.I.l p

e a

t_ _.

~~

i 7lI

{

_I o

3.

,l4.i o

6 v

l_z_ 7_i f_

7 _..

9 o

a L,g

[T t.

r 0

.[5;

,f l.

34i

.l i f.,.

I4,. ;.

f.e. li

, g _ f.

0

.. _ g._ _

_7, I.

I I1

.lq!

a

. 7 i

I

} Ii_

g.le l.T o

.t

.. p;l ee7.h; m_

pI,.

s a

o A

v r

1 4

{

f.,.

.le!

1

_._t lqT 4_

?

e n

. i4_1he s

3

_ Isis %. _I L.i f..

_, 7

_ij

)

ipI

.(i.m..p+

i,

e. !,i

.p4

.i7_i a

i. ip;. ij#

i+i-.

,i 4_

A ij.yi{9 m7.!,

+!L'4 pir.

_ r l_ n~..

. I, i,.

le d.l

.. !p!

o J

.!e.

.. f.t_ '7 l,T

! i.. j...i.!

o R

!pr

.i1_

_ ~

o 3

c e.n.3 J.

a

. _ I.

. i.,

.l4 t

3

_ ~

_ ~

l4I

.l.!

}.le

.i 4_

_ + _ _ P _ le. T..

u

.. ~..

d U

.q 7 t

-.. _ - _. ~... _..

6 i

.qil J. q.

. 7. g. !,

e_! I

.I,.T f.1 4_

o A'

d

,i

.Iw!4

}2i 4_

.l y

l,.1 s n i #. I.

o 8

=i4 2_

z s 3

.i eI,r

,ig 3

g l+!.

}

• Ii.

. _ 7. 7.1,.

ed V

1 4_.

[+!

e

}4 j

l p

S ih q77 7_4i l,i_

I+

o n q.I,F __.

4

.!ti

. 7

!+7 d

l"!

W

. p

7. 7, I; 4r-I1 !m

.! -1b.i(

o n

l f._

o d

o

_ l.I

9. :

p,._!ti I+:

_. I.i mi[1 _ _. _

. ~

,I Lm

.. t.

z U

. _.i-

.!j

-.'I, t.I!+

7 _i, e.t O

q37_lr.i4_n4_

3. i1l pI i.

7.t{,.

!b!

.I+r i_ -.. -

7_.. -

l!

p i

• gil, 7

_.iw3 4

t

.l

> 2_ 7id_ ;_

. i 4

[

_!._n

_I n ;_,.

!P!.

o R

it.

7_

o

+

It!

s 3

.!el.

i,p J

! I.t

'e_

_. ~.

.'y

_ g i!

t

.Isil *pp!y7.

Q

.I p

4_

J_ - _.-

4

.it!

r.

d!.

~.

4 a

f_ pije7 l3 7}4 t_. -* l_7

!O.. _ -

i f.

H

!4_!.

. 7. i{t._7 pl-.i1.F

_l.T

.I+

I

.i 6 '~,_. J --

4_. -

o f

!iI 1

e d._

.. p o

U 4

9 o

a i,T.

I.

14p7

. 8

_,p!s f

.m_!i.

.I l

p

[t i

W 3

Iu!w).

_7. 7. D. _

.B

!4r u

>pr l+

lt3kti[;.7.g U _. tr. l".

4.

3

)

.l4. t' 7 !p

_4 G _g.p.ir,1m "i4_ ;

+

!,.I, l.

1jr U

o O

!1'.

y _ -

e.

3

_. m

.!+

- j 4 t !+i o

j.

In i.

p !l.T

!p I!

}._ llij _ _ _

[

p s

[e.fUT

• 4_n.

e.

i7i i_ _

Ti4p7

-7_. - -

b_

I4 1jj

.!+5 g

~

i.. _

jj

!+I E

-Ii

pg7p, L_

- i _

r 7

_I,.T

.!+

.- !*i 3

4 j;

p!+ 'r

-l._

~

o H

()

o o

o o

o 0

o S

,0 l

o o

o o

o j

s s

y e

g

goq p

c,3y :E-m o.... gw ' g**"s e

e J.a 8"N

CONTAINNENT SYSTENS RECIRCULATION SPRAY SYSTEN LINITING CONDITION FOR OPERATION 3.6.2.2 Two independent Recirculation Spray Systems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With one Recirculation Speay System inoperable, restore the inoperable system 1

to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable Recirculation Spray System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be 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 />.

SURVEILLANCE REQUIRENENTS l

4.6.2.2 Each Recirculation Spray System shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path is not locked, sealed, or otherwise secured in position, is in its correct l

position; b.

By verifying, that on recirculation flow, each pum,n meets the acceptance criteria specified in Figure 3.5-1 when tested pursuant to Specification 4.0.5; c.

At least once each REFUELING INTERVAL by verifying that on a CDA test signal, each recirculation spray pump starts automatically after a 660 i20 second delay; d.

At least once each REFUELING INTERVAL, by verifying that each automatic valve in the flow path actuates to its correct position on a CDA test signal; and e.

At least once per 10 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

4 E

4 NIgLSTONE-UNIT 3 3/4 6-13 Amendment No. pp, JPP, J77,

3 Docket No. 50-423 B16463 i

d 1

'1 i

Millstone Nuclear Power Station Unit No. 3 Proposed Revision to Technical Specification Recirculation Sorav System Surveillances (PTSCR 3-24-97)-

l Backaround and Safety Assessment 4

4 i

i 1

i l

i i

i 1

l 2.

i l

i May 1997 4

J

U.S. Nucirr Rrgul: tory Commission s

B16463\\ Attachment 4\\Page 1 Backaround j

Technical Specification Surveillances 4.5.2.f and 4.6.2.2.b currently require that each Recirculation Spray System (RSS) pump develop a differential pressure greater than or equal to 130 psid when tested according to the requirements of Specification 4.0.5. The proposed changes will modify the surveillance acceptance criteria to require that each

]

pump develop a differential pressure greater than or equal to the pump performance curve contained on Figure 3.5-1 when tested according to the requirements of Specification 4.0.5.

Safety Assessment 4

Technical Specification Surveillances 4.5.2.f and 4.6.2.2.b require that each RSS pump i

develop a differential pressure greater than or equal to 130 psid when tested according to the requirements of Specification 4.0.5 to meet its surveillance requirements.

Specification 4.0.5 establishes the inservice requirements required by 10CFR50.55a for class 1, 2, and 3 pumps and valves. The proposed changes will modify the j

surveillance acceptance criteria used to demonstrate operability of the RSS pumps.

The new acceptance criteria for the RSS Tectnical Specification surveillance will modify the surveillance acceptance criteria to require that each pump develop a differential pressure greater than or equal to the pump performance curve contained on i

Figure 3.5-1 when tested according to the requirements of Specification 4.0.5.

Because it is undesirable to test the pumps on recirculation flow to the RWST, pump testing will now be performed at lower flows than previously performed. Consistent with Specification 4.0.5, one point on Figure 3.5-1 will be used to meet the proposed l

surveillance acceptance criteria.

Periodically comparing the reference differential pressure developed at this reduced flow detects trends that might be indicative of pump degradation. The proposed pump performance curve is above the accident analysis curve and is more restrictive than the current inservice inspection curve in the accident analysis region.

The proposed pump performance curve has been degraded in accordance with the recommendations of ASME XI for the full range of flow and will be i

used to meet the surveillance requirements. These changes have no adverse impact on the RSS system operation and do not degrade the reliability of the system.

These changes to the Technical Specifications are necessary because each of the RSS pumps will now be tested without impacting the RHR system at power operations.

This change will delete the necessity of using a dedicated operator at Residual Heat Removal (RHR) manual valve 3RHS*V43 during future RSS surveillance testing. In the past, a dedicated operator has been credited to close this manual valve should a SIS signal be received. This RHR valve will remain in the closed position during power operations.

J

3 U.S. Nucl:ar R:gulttory Commission B16463%ttachment 4\\Page 2 i

The proposed changes will not increase the probability of occurrence of an accident or l

malfunction, they will not increase the consequences of previously evaluated accidents or malfunctions and will not introduce a malfunction or accident of a different type. The changes will not increase public risk and are therefore safe and do not raise an j

unreviewed safety question.

5 I

4-e I

d t

J i

i i

1 l

l 3

k i

f 4

a

_~

a Docket No. 50-423 l

B16463 1

4 Millstone Nuclear Power Station Unit No. 3 Proposed Revision to Technical Specification Recirculation Sorav System Surveillances (PTSCR 3-24-97)

Sianificant Hazards Consideration and Environmental Considerations May 1997

l>-

U.S Nucl=r R:gulatory Commission B16463%ttachment 5\\Page 1 i

Sianificant Hazards Consideration NNECO has reviewed the prcposed revision in accordance with 10CFR50.92 and has j

concluded that the revision does not involve a significant hazards consideration (SHC).

l The basis for this conclusion is that the three criteria of 10CFR50.92(c) are not satisfied. The proposed revision does not involve a SHC because the revision would not:

l 1.

Involve a significant increase in the probability or consequence of an accident j

previously evaluated.

l The proposed changes to Technical Specification Surveillances 4.5.2.f and 4.6.2.2.b will modify the surveillance acceptance criteria to require that each Recirculation Spray System (RSS) pump develop a differential pressure greater than or equal to the pump performance curve contained on Figure 3.5-1 when tested according to the requirements 'of Specification 4.0.5.

Because it is undesirable to test the pumps on recirculation flow to the RWST, pumr testing will now be performed at lower flows than previously performed. Consistent with j

Specification 4.0.5, one point on Figure 3.5-1 will be used to meet the proposed surveillance acceptance criteria.

Periodically comparing the reference l

differential pressure developed at this reduced flow detects trends that might be i

indicative of pump degradation. The proposed changes are consistent with RSS pump design criteria and performing surveillance testing does not significantly

{

increase the probability of an accident previously evaluated.

The proposed changes to modify the surveillance acceptance criteria to require that each RSS pump develop a differential pressure greater than or equal to the pump performance curve provides the necessary assurance that the pumps will function as required in previous evaluations and does not significantly increase l

the consequence of an accident previously evaluated I

Therefore, the proposed changes do not involve a significant increase in the l

probability or consequence of an accident previously evaluated.

i 2.

Create the possibility of a new or different kind of accident from any accident i

previously evaluated.

i The proposed changes to the surveillance acceptance criteria of the RSS pumps does not change the operation of the Recirculation Spray System or any of its i

components during normal or accident evaluations.

i j

Therefore, the proposed revision does not create the possibility of a new or different kind of accident from any accident previously evaluated.

.l i

)

3 a.---

w

-(

U.S. Nucl::cr Regulttory Commission B16463%ttachment 5\\Page 2 1

3.

Involve a significant reduction in a margin of safety.

The proposed changes will change the surveillance requirements needed to demonstrate operability for each of the RSS pumps. Technical Specification Surveillances 4.5.2.f and 4.6.2.2.b will now require that each pump meet its acceptance criteria in accordance with Figure 3.5-1 when tested according to the requirements of Specification 4.0.5. Figure 3.5-1 will be inserted into the Technical Specifications.

The new acceptance criteria for the RSS Technical Specification surveillance is above the accident analysis curve and is more. restrictive than the current-inservice inspection curve in the accident analysis region. The proposed TS curve has been degraded in accordance with the recommendations of ASME XI for the full range of flow and will be used to meet the TS requirements.

Therefore, the proposed revision does not involve a significant reduction in a margin of safety.

in conclusion, based on the information provided, it is determined that the proposed revision does not involve an SHC.

Environmental Considerations NNECO has reviewed the proposed license. amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed revision does not involve a SHC, does not significantly increase the type and amounts of effluents that may De released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, NNECO concludes that the proposed revision meets the criteria delineated in 10CFR51.22(c)(9) for categorical exclusion from the requirements of an environmental considerations.

l l