ML20235G690

Amends 125 & 128 to Licenses DPR-44 & DPR-56,respectively, Revising Tech Specs Re Reactor Core Thermal Hydraulic Stability & Operation W/Jet Pump Flow Indication Failures & Jet Pump Operability Surveillance Requirements

ML20235G690
Person / Time
Site:	Peach Bottom
Issue date:	09/24/1987
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235G694	List: ML20235G690 ML20235G703
References
NUDOCS 8709300159
Download: ML20235G690 (21)

Text

_ _ _ _ _ ___

~

g*,,3 AICp o

UNITED STATES

'g

[',

g NUCLEAR REGULATORY COMMISSION E

WASHINGTON, D. C. 20555

\\...../

PHILADELPHIA ELECTRTC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COM M DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 125 License No. DPR-44 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated January 12, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFP.

Chapter I.

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health or safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendmert, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:

l 8709300159 870924 PDR ADOCK 05000277 P

PDR

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 125, are hereby incorporated in the license.

PEC0 shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/s/

Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: September 24, 1987 l

g 3Li

,/Mt7

?

M0{ h PDl-2/P 0

\\

PDI-2/D PD

(, ('h h

RJC$ ark

\\

WButler

/87 c1/%/87 1/87 C/g87

\\

f-

.p

=

\\

1 '(2) -Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 125, are hereby incorporated in the license. PECO shall operate the facility in accordance with the l

Technical Specifications,

3. - This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler Director Project Directorate 1-2 Division of Reactor Projects 7/II

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 24, 1987

)

i l

l I

11 ATTACHMENT TO LICENSE AMENDMENT NO.125 FACILITY OPERATING LICENSE ND. DPR-44 DOCKET NO. 50-277-Replace the-following pages.of the Appendix'A' Technical Specifications with the enclosed pages. The revised areas are indiceted by marginal lines.

Remove Insert

-10 10 148 148 J-149 149 149a 149b 160.

160 164d 1

1 E

4 PBAPS UNIT 2 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTINO 2.1.A (Cont'd)

In the evert of operation with a maximum f raction of limiting power density (MrLPD) greater than the fraction of rated power (FRP), the setting shall be modified as follows.

S $ (0.58 W + 62% -0.58 AW)(TRP)

HTLPD

where, FRP = fraction of rated thermal power (3293 MWt)

MFLPD e maximum fraction of limiting power density where the limiting power density is 13.4 KW/ft for BP/P8X8R fuel

?

and 14.4 KW/ft for GE8XBEB and LTA310 fuel.

The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.

2. APRM--When the reactor mode switch is in the STARTUP position, the APRM scram shall be set at less than or equal to 15 percent of rated power.

3. IRM--The IRM scram shall be i

set at less than or equal to

{

120/125 of full scale.

1 i

l j

i l

I i

Amendment No. f6, 84, 56, 42,.(6, l 19,18,113.125 1

e V>

PBAPS Unit 2 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.E Jet Pumps 4.6.E Jet Pumps-

1. Whenever the reactor is in

1. Whenever there is recirculation

-the startup or run modes flow with the reactor in the all jet pumps shall be startup or run modes, jet operable. If it is determined pump operability shall be that a jet pump is inoperable, checked daily by verifying an orderly shutdown shall be that the following initiated and the reactor shall conditions do not occur

'be>in a Cold Shutdown within

. simultaneously:

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. Flow indications from each of a) The two recirculation loops ' ave h

the 20 jet. pumps during two a flow imbalance of 15% or loop operation or 10 jet pumps more when the pumps are during single loop operation operated at the same speed.

shall be verified prior to initiation of. reactor startup b) The indicated value of core flow from a cold' shutdown condition.

rate varies from the value derived from loop flow measure-ments by more than 10%.

3. The indicated core flow is the sum of the flow indication from each of the 20 jet. pumps.

c) During two loop operation, the l

Flow indication from no more diffuser to lower plenum than one jet pump shall differential pressure reading be unavailable during two on an individual jet pump loop operation.

If varies.from the mean of all two or more jet pump flow jet pump differential pressures indication failures occur by more than 10%.

during two loop operation, an orderly shutdown shall d) During single Icop operation, be initiated within 12 diffuser to lower plenum hours and.the reactor differential pressure reading shall be in cold shutdown on an individual jet pump in condition within the the operating loop varies following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

from the mean of all jet pump-differential pressures in the

4. During single loop operation, operating loop by more no jet pump flow. indication than 10%.

failures in the operating loop are permissible. If a jet pump

2. Additionally when operating with flow indication failure occurs one recirculation pump with during singic loop operation, the equalizer valves closed, an orderly shutdown shall be the diffuser to lower plenum initiated within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and differential pressure shall be the reactor shall be in cold checked daily and the differential shutdown condition within the pressure of any jet pump in the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

idle loop shall not vary by l

more than 10% from established l

pattern.

3. The baseline data required to evaluate the conditions in L

specification 4.6.E.1 and l-4.6.E.2 will be obtained each operating cycle.

Amendment No. J$, AS, 75,125

-148-

4 I

I 1

a i

PBAPS Unit 2 LIMITINC CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.F RECIRCULATION PUMPS 4.6.F RECIRCULATION PUMPS

1. Following one-pump operation,

1. Establish baseline APRM the discharge valve of the low and LPRM neutron flux noise speed pump may not be opened values for each operating mode unless the speed cf the faster at or below the Thermal Power pump is less than 50%

specified by Line A in Figure 3.6.5

{

of its rated speed.

for the region for which monitoring i

is required (Specification 3.6.F.5,

)

REGIONS I and 2) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of entering the region for which monitoring is required unless

2. The requirements applicable to baselining has previously single loop operation as been performed since the identified in sections 1.1.A, last refueling outage.

2.1.A, 2.1.B, 3.5.I & 3.5.K l

shall be initiated within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.following the removal of one recirculatier. loop from service, or the unit placed in Hot Shutdown condition within the fo11owing'6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

3. Whenever the reactor is in the startup or run modes, two reactor coolant system recirculation 1 cops shall be in operation and the reactor shall not be operated in REGIONS 1 or 2 of Figure 3.6.5 (defined below),

except as specified in 3.6.F.4 and 3.6.F.5

a. REGION 1 - Total core flow less than 39% of rated and Thermal Power greater than the limit specified by Line A in Figure 3.6.5.

b. REGION 2 - Total core flow greater than or equal to 39%

of rated, but less than or equal to 45% of rated and Thermal Power greater than the limit specified by Line A in Figure 3.6.5.

4.

With only one reactor coolant system recirculation loop opera-ting, immediately initiate action to avoid operation in REGION 1.

Thermal Power shall be reduced and be below the limit specified by Line A in Figure 3.6.5 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or core flow shall be increased to greater than or equal to 39%

of rated core flow within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

-149-Amendment No. J/>, AB,125

l j

.PBAPS Urilt 2-LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS

.)

l 3.6.T RECIRCULATION PUMPS 4.6.F RECIRCULATION PUMPS 5.

During operation in REGIONS I

1 or 2 of Figure 3.6.5:

)

a.

The surveillance requirements 2.

After entering the region of 4.6.F.2'and 4.6.F.3 must for which monitoring is be satisfied.

required. determine APRM and LPRM noise levels within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and

(

3.

After the completion of-a Thermal Power increase of at least 5% of Rated Thermal Power, determine APRM and LPRM j

noise. levels within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b.

With the APRM or LPRM neutron flux noise 3evels greater than 4% and three times their established baseline noise levels, immediately initiate corrective action to restore the noise levels to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or begin an orderly shutdown and be in Hot Shutdown within the-next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, unless the noise levels are restored within the required limits during this period. Detector levels A and C of one LPRM string per core octant plus detectors A and C of one LPRM String in the center of the core should be monitored.

6.

With no reactor coolant system recirculation loops in operation and the mode switch in GTARTUP or RUN, immediately initiate action to reduce Thermal Power to less than or equal to the limit specified by Line A in Figure 3.6.5, and place the reactor in at least Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Anendment No. 125

-149a-l l

l L.

[>

I. ' '

.4 1

.a

. Unit 2'

PBAPS LIMITING CONDITION FOR OPERATION

-SURVEILLANCE REQUIREMENTS 3.6.G STRUCTURAL INTEGRITY-4.6.G STRUCTURAL-INTEGRITY

'The structural integrity of ~

The non-destructive inspections the primary system boundary listed in Table 4.6.1 shall be shall be maintained at-the performed as specified. The level' required by the results obtained from.

original acceptance standards-compliance with the specification.

throughout.the life of the.

will be evaluated after

. station.- The reactor =shall' 5 years and the conclusions be maintained in a Cold of this evaluation will be Shutdown condition until reviewed with the NRC.

each indication-of a defect.

has been investigated and evaluated.

1 Amendment No. 125

-149b-1 i

l o-

t Unit 2 PBAPS 3.6 F & 4.6.F BASES l

Jet Pump Flow Mismatch, Flow Indication and Thermal Hydraulic Stability Requiring the discharge valve of the lower speed loop to remain closed until the speed of faster pump is below 50%

of its rated speed provides assurance when going from one to two pump operation that excessive vibration of the jet pump risers will not occur.

Operation with one recirculation loop in service is permitted.

In such instances, the designated adjustments for APRM rod block and scram setpoints, RBM setpoint, MCPR fuel claddicc integrity safety limit, MCPR operating l

limits, and MAPLHGR limits are required.

Also, single loop operation with any jet pump flow indication failures

{

is an unanalyzed condition and, therefore, warrants a shutdown. One jet pump flow indication failure during two-loop operation is acceptable, but more than one failure has not been analyzed and, therefore, warrants a shutdown.

Thermal power and core flow limitations are prescribed in accordance with General Electric Service Information 4

Letter No. 380, Rev. 1, "BWR Core Thermal Hydraulic Stability," dated 2/10/84.

Neutron flux noise limits are established to ensure early detection of limit cycle neutron flux oscillations.

BWR cores typically operate

{

with neutron flux noise caused by random boiling and flow

{

noise. Typical neutron flux noise levels of 1 to 12% of rated power (peak-to-peak) have been reported for the range of low to high recirculation loop flow during both 3

single and dual recirculation loop operation. Neutron I

flux noise levels significantly larger than these values i

are considered in the thermal / mechanical fuel design and are found to be of negligible consequence, and in compliance with stability licensing criteria. In

{

addition, stability tests at operating BWR's have i

demonstrated that when stability related neutron flux limit cycle oscillations occur they result in peak-to-peak j

neutron flux limit cycles 5 to 10 times the typical values.

Therefore, actions taken to reduce neutron flux noise levels exceeding three (3) times the typical value are sufficient to ensure early detection of limit cycle neutron flux oscillations.

Data to establish baseline APRM and LPRM neutron flux noise values is obtained at or below the power specified l

in Figure 3.6.5 for use in monitoring noise levels during operation in the region for which monitoring is required.

l Amendment tb. 27, 77, 125

- 160 -

l l

l

Urd t 2 PBAPS er-

.t..

. 5......

.j g.

g g.

q I

ri.

t,

I,

It:

-::a l

It: 1 t!It

i

.T _

T..! :ji.,1 'I.

.i ii.e

.g ).p

.; i. c., :.,;

I, l, l '.e,- - wi.

,,t,!..

.t. T, ; j.l". l..

u !. i. -I

• :.,1 4

. i. t..., i.

t l,lj

' it ijl

}*

U..l. j ;. lldl!

l I

!!! ',j'

+,.tfH rN ' i t i

. M.

..p t

. j l.

b' 4hr' i..,2 i.*i

. '2 d-l.! :1.h

' k~rl-i.

I 7

.i g

..+.

..e... J.

' t.

j jaj,Ig

.j.

~

i r.

...v.

i..

.,, g hi i 11

.,l 14Hj i ll!!!

+:4-.,Jhi.l-

• l4 i:

nl I

I :i:u

,a i.. m n :'

m.;

4 j_tr l.t.l.7.'p.

g

ll!

';?!

l t'ij l

j8Njl!!

8'

T'

" ij t i dil l&di i r/l

?

1, ful I

fi. _

q 4

,.;,,.4, - m

..i.

... t v i

.i s.. i.i.

s i.....i

. m,

,i n i.

.. q.

, g I l !,.

a 1

l 3

M ti El M, il.

i' h.;..l; 'I T,

-l

~,

!!;i i

l,,I i,..

i:

"i:

.il.:, :

.S ;:

g+.. ->}.ptr1.: :::i a nji j!

l i,a

,oi

,;'q m j. r,.,...,;::t

.s i l.. -

.. h.. ; u.

..,. a 1. :.

g a,....u.

.:1.

y

tal4

.t=.r trer

n.; m

-Y

. ;p,:

N M J:I,ylf3 : i.dl:

.:. 3.2:

Bg

- %.- m; _._",. J :: = i d..

c a

"~i S

.[,l.1 *;l

• r:

rui' p ri :

• l. T.'

9CJ M-T.

. ig.w N- #:#;r.. dTmi,{1:r.t.j:r.'. : '.I1

-I.TSt 11 l!I l.I fI y

~ W W:

w ci

,v.,.,..

c.- i...

c.,

E

...i. ry.7 1 :4. n..I lt

-; : :.i.'

el g:.'" T;.- T,-r r

c-w a

g g

g.

.T

..II.I,..T. T. 1'-r

. +

.,p::..

• . !.1l..',

l

+

-l.I.-

T.

g

-g r.T..

T....

u,;

g.

i ri g.

.: r

.:::- - ;;;; g"-

p-g*

H--,. Ev;.

....j...

,.i,

...,n

.j;

.+,-

.r.

,.r

,,ii

..u,...

i

'l i,i 8

.,, I i 1'

6,

,t 4.

'l

..t.

.t I

_a u

.4.;

t _u.

e i ;.

g

..:.:/ 1;..; : ::

t:

l s,

l, l

o 1

g g

.a Ii I i

i i a

3

.g.

.s

24

. :r. :.. 1;ri

.t.; ;..:.t ; :.:Ti I.

Y.. lj[j ;17l 1.I ' I !!!:

!t: F l,1 l

l:

g t.;

Y.;s..

ii.i

.;I M '.! I!!

i;;;

$@,.i.E

-3T TfL!. :T 9ff.1...j.

TS 1

. $ '; ' t.I.Z:!. 4cd

u..i

\\:.

.o.,L.,.

.1,.

i,,.

s l.,l

, l,...

.i c.+.

t 11 d

M.

d 5,

S.

5.

(PiBWd 70 %) )CEMOd 'IM IFI, EECD Amerdment No.125

-164 :t-

d e r 00 080g

~#

o UNITED STATES

[

'i NUCLE AR REGULATORY COMMISSION

-l WASHINGTON, D. C. 20555

^h,

,$~

a...+

PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GA5 COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.128 License No. OPR-56 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated January 12, 19P,7, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I.

B.

The facility will operate in confnnnity with the application, the provisions of the Act, and the rules and regulations of the Comission; -

C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the' comon defense and security or to the health or safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:

I I'

L

e

, o (2)

Technical ~ Specifications The Technical.' Specifications contained in Appendices A and B, as revised through Amendment No.128, are hereby. incorporated in the license.

PEC0 shall operate the facility in accordance with the Technical Specifications.

3., This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/s/

Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects I/II

Attachment:

Changes-to the Technical Specifications Date of Issuance:

september 24, 1987 TAA 27 @

lp. 9 M S 7 l

c.

1 Og \\ gg~

PDI-2/

PDI-2/P PDI-2/D M(fiQ$

RJClark, WButler q/

87 07/g/87 p8

/g7

___e___----_.-__.._._--.._

i 4

' (2)

Technical Specifications The. Technical Specifications contained in Appendices A and P, as

. revised through Arendment No.1224 are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects 1/II

Attachment:

Changes to the Technical Specifications Date of Issuance: September 24, 1987 I

..[*

C.

ATTACHMENT TO LICENSE AMENDMENT NO.128.

FACILITY OPERATING LICENSE NO. DPR DOCKET NO. 50-278 Replace'the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Insert i

148-148 149 149-149a 149a 149b-149b 149c 160 160 164d 164d i

_...-.m

e

.,,3

'g PBAPS Unit 3 LIMITING CONDITION FOR OPERATION-SURVEILLANCE REQUIREMENTS 3.6.E Jet Pumps' 4.6.E Jet Pumps 1.: Whenever the reactor is in

1. Whenever there is recirculation' the startup or run modes,.

flow with the reactor in the allojet pumps shall be startup or run modes, jet operable. If it is determined pump operability shall be-l that a jet pump is inoperable, checked daily by verifying an orderly shutdown shall be that the following initiated.and the reactor shall conditions do not occur be in.a Cold Shutdown within simultaneously:

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. Flow indications from each of a) The two recirculation loops have the 20 jet pumps during two a flew imbalance of 15% or loop operation or 10 jet pumps more when the pumps are during single-loop operation operated at the same speed.

shall be verified prior to i

initiation of reactor startup b) The indicated value of core flow I

from a cold shutdown condition.

rate varies from the value derived from loop flow measure-l ments by more than 10%.

3. The indicated core flow is the sum of=the flow indication from each'of the 20 jet pumps, c) During two loop operation, the l

Flow indication from no more diffuser to lower plenum than one; jet pump shall differential pressure reading be unavailable during two on an individual jet pump loop operation.

If varies from the mean of all two or more jet pump flow jet pump differential pressures indication failures occur by more than 10%.-

during two loop operation, an orderly shutdown shall d) During single loop operation, be initiated within 12 diffuser to lower plenum hours and the reactor differential pressure reading shall be in cold shutdown condition within the on an individual jet' pump in the operating loop varies following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, from the mean of all jet pump differential presures in the

4. During single loop operation, operating loop by more no jet pump flow indication than 10%.

failures in the operating loop are permissible. If a jet pump

2. Additionally when operating with flow indication failure occurs one recirculation pump with during single loop operation, the equaliser valves closed, an orderly shutdown shall be the diffuser to lower plenum initiated within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and differential pressure shall be the reactor shall be in cold checked daily and the differential i

shutdown condition within the pressure of any jet pump in the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

idle loop shall not vary by more than 10% from established pattern.

3. The baseline data required to evaluate the conditions in l

specification 4.6.. 1 and 4.6.E.2 will be obtained-I each operating cycle, b

Amendment No. IA, 25, pp,128

-148-

PBAPS Unit'3 LIMITING CONDITION FOR OPERATION SU,RVEILLANCE REQUIREMENTS 3.6.F.. RECIRCULATION PUMPS 4.6.F RECIRCULATION PUMPS

1. Following one-pump operation,

1. Ert...lish baseline APRM the discharge valve of the low ard LPRM neutron flux noise speed pump may not be opened values for each operating mode unless the speed of the faster at or below the Thermal Power pump is less than 50%

specified by Line A in Figure 3.6.5 of its rated speed.

for the region for which monitoring is required (Specification 3.6.F.5, REGIONS 1 and 2) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of entering the region for which monitoring is required unless

2. The requirements applicable to baselining has previously single loop operation as been performed since the identified in sections 1.1.A, last refueling outage.

2.1.A, 2.1.B,'3.5.I & 3.5.K l

shall be initiated within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the removal of one recirculation loop from service, or the unit.placed in Hot Shutdown condition within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

3. Whenever the reactor is in the

-startup or run modes, two reactor coolant system recirculation loops shall be in operation and the reactor shall not be operated in REGIONS 1 or 2 of Figure 3.6.5 (defined below),

except as specified in 3.6.F.4 a nd -3. 6.F. 5

a. REGION 1 - Total core flow less than 39% of rated and Thermal Power greater than the limit specified by Line A in Figure 3.6.5.

b. REGION 2 - Total core flow greater than or equal to 39%

of rated, but less than or equal to 45% of rated and Thermal Power greater than the limit specified by Line A in Figure 3.6.5.

4.

With only one reactor coolant system recirculation loop opera-ting, immediately initiate action to avoid operation in REGION 1.

Thermal Power shall be reduced e

and be below the limit specified by Line A in Figure 3.6.5 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or core flow shall be increased to greater than or equal to 39%

of rated core flow within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

-149-Anendment No. JA, 77, Iff,128 l

l i.

______ _ o

V i.

,)

l.

PBAPS Unit 3 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.T RECIRCULATION PUMPS 4.6.F RECIRCULATION PUMPS 5.

During operation in REGIONS 1.or 2 of Figure 3.6.5:

5.-

The surveillance requirements-2.

After entering the.rrgion of 4.6.F.2 and 4.6.F.3 must for which monitoring as be satisfied.

required, determine APRM and LPRM noise levels within one hour and at least once per B hours, and 3.

After the completion of a Thermal Power increase of at least 5% of Rated Thermal Power, determine APRM and LPRM noise levels within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b.

With the APRM or LPRR

, neutron flux noise levels i

greater than 4% and three times their established i

I baseline noise levels, immediately initiate corrective action to restore the noise levels to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or I

begin an orderly shutdown anc be in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, unless the noise levels are restored within the required limits during this period. Detector levels A and C of one LPRM string per core octant plus detectors A and C of one LPRM string in the center of the core should be monitored.

l 6.

With no reactor coolant system recirculation loops in operation and the mode switch in STARTUP or RUN, j

immediately initiate action j

to reduce Thermal Power i

to less than or equal to the limit specified by Line A in Figure 3.6.5, and place i

the reactor in at least Hot l

Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

i l

1

'Amendnent No. M, 128

-149a-1 l

l

~___-___-_-_-_-_U

m

,n.

X.

Unit 3 I

PBAPS LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.G STRUCTURAL. INTEGHITY 4.6.G STRUCTURAL INTEGRITY 1

The structural integrity of The non-destructive inspections the primary. system boundary.

listed.in Table 4.6.1 shall be shall be maintained at the-performed as specified.

The level required by the results obtained from original acceptance standards compliance with the specification throughout the life of the will be evaluated after station.

The reactor shall 5 years and the conclusions

-be-maintained in a Cold of this evaluation will be Shutdown condition until reviewed with the NRC.

each indication of a defect t'

has been. investigated and evaluated.

i a

1 l

-149b-I 1

Amendment No. M,128 i

l i

l i

4

Unit 3 PBAPS 3.6.F & 4.6.F BASES l

Jet Pump Flow Mismatch, Flow Indication and Thermal Hydraulle Stability

\\

Requiring the discharge valve of the lower speed loop to remain closed until the speed of faster pump is below 50%

of its rated speed provides assurance when going from one to two pump operation that excessive vibration of the jet pump risers will not occur.

I Operation with one recirculation loop in service is permitted.

In such instances, the designated adjustments for APRN rod block and scram setpoints, RBM setpoint, MCPR fuel cladding integrity safety limit, MCPR operating limits, and MAPLHGR limits are required.

Also, single loop operation with any jet pump flow indication failures

.is an unanalyzed condition and, therefore, warrants a shutdown, One jet pump flow indication failure during two-loop operation is acceptable, but more than one failure has not been analyzed and, therefore, warrants a shutdown.

Thermal power and core flow limitations are prescribed in accordance with General Electric Service Information Letter No. 380, Rev. 1, "BWR Core Thermal Hydraulic Stability," dated 2/10/84.

Neutron flux noise limits are established to ensure early detection of limit cycle neutron flux oscillations.

BWR cores typically operate with neutron flun noise caused by randoin boiling and flow noise. Typical neutron flux noise levels of 1 to 12% of rated power { peak-to-peak) have been reported for the range of low to high recirculation loop flow during both single and dual recirculation loop operation. Neutron flux noise levels significantly larger than these values are considered in the thermal / mechanical fuel design and are found to be of negligible consequence, and in i

compliance with stability 3icensing criteria.

In j

r addition, stability tests at operating BWR's have

{

demonstrated that when stability related neutron flux i

limit cycle oscillations occur they result in peak-to-peak t.eutron flux limit cycles 5 to 10 times the typical values. Therefore, actions taken to reduce neutron flux noise levels exceeding three (3) times the typical value are sufficient to ensure early detection of limit cycle neutron flux oscillations.

Data to establish baseline APRM and LPRM neutron flux noise values is obtained at or below the power specified l

in Figure 3.6.5 for use in monitoring noise levels during operatien in the region for which monitoring is required.

j i

4 I

Amendment No. JA, 77, JM,128 - 160 -

I t

I 1

I

y&

-.c l

l PBAPS Unit' 3 k

i Cr-i i.

i

.i, l..

2q[ --lj I

h,,.1 l l

,li.l1 i

i g.

,,1.1.;

l ;I t!i!

q. l!:l :: :

l

t,

r,

..:l

[ j;j!I;jl. l l' ;

+

-.,"lETi.,.'.d 4,:]l'..l j:l l.;l,l :!t.. !,

g1 4 'j...! r' i t '.

r

.:: 1 ll 2,.I j :,

l r j

1,,.

i' I. 'l, I'l

1. l

...~

ill I. itl-

. d: o,.r.. mrf.,

.4.,.. j j-.i, ql l.

er, t j & -N 8 ! ! I i,-4 [- i 1

i..I,.r r.

,l-

i. l.

,,tl.::.:.

+.

e,

.+

1l

.1

,. 1 l

.;.l l-l lt : l. l.

]'

l

! ),,1 l l

1

.I

i. g i*g[

I.

- -.p.. _. g..

(..;

+ -f 3 i

.,i i

".p:.T.h :)

l l

1.

1 i

Il!

ll'l.l l!;il.l 1: I

.4['.Q.

j l llll l'!

ll.

11 L

i

!!!l

.J.[.l.':4[., l-

=

1-i.

111 wW

/p

. 6.\\,.4.g

'.4......

i i

..,i q

i i

i

!. lii i p'1 i.

y-v.i

'l

'l l

+

1] 1'

'li.l I' l :,

i h/l J. l' ll l

h'l l

f tT.h?T....'

4. '.;,.

q

,ii;

...;ij.i gg 5

.s..

j..,

1 lii j.

.<...t

i.,

'l T !!ii.f..,

.b..g.,

,l;;

9 JT4tlh.T! Il.

T1~

l 1

i

.I ii..

$"'[

W. H, !. !, ' '

! ! - l

,h

bll!!j !lli!:::

.:;l.

ii! li :

l j;:! ;!l. :

.: 1 l. :

,g A'r:."?.T7-1: 171 I..r4..t.:

' ::n.:li:

r

.4'G- * '1' d

-..Jm

_d-**---+

W i :-y: nya =; c.:.? *1Tip,;-.t":s "a,e,

,_ -t-me - m w.:. d n.

i.r-

"!dl-l S

9Ed M*.,,.:::p-d'lh6.-,,..E E'.)..,{.1$

l!T.' ll!';!dT k:

n.r.

..tr.gp rr ; :. T-. I.N -I!::

l y

. fi i 9 g'" r i w,..

..u

'(.... ; !,$,.I.g *

24. !..!g,.....

.,.M..g s-, g.'-~.1,h,,h d

'.. l )-

"l E

.1, g,

1..

1 y.c w C

5 Ji: J E=

+H. - +

- a.i b

'a +

.:. :..-.3.-

T. l, ' 3..N.-

-4

r a e-

jg6 8

1 l

.L T.I, 1:

g *,,g

rJ.lT T.., ir j;;;. l. 7..

e, c4. :,..! f' eg-

, 47. :

.: #.... ; ;. c;::t,.,..:,

[

'=

T. t.

.f.

.I...,..l.

7,..[

.,... i u.,.,.

,,e

l l

t i Il.

3; l lj*-4{.c i

j l

illl i

.r... f- !.l i

.h k

5.-

. i.,

c

. i.o.

u..

.o4

.: i, :.

8 Ie I ~i

.:;-'- /.::.*..:..* ;

=:

• /~ ;

i ik,i

.U. !

I I 1

.r.1

. 'i:1o

.m,.i i,., : i n.

o gi'llI.

r...,.,.

.. w.

% lj{.)

l,1;

'::' Ij j! i:1:

l: : ;;

ll 1 Eg

\\".::,.

i f.l

.;i

• ;..I l'l i;;;

I W:1 *. '; ;!.I.Z.t.

f,

{if1.,'

.,.p.

4:st k '7!.!. :T4 ti.;.

T.

.. j...! i,.; ;;..

.pi

\\:..

,i.' id.. :

; i....l.I !

. i:

.q d

5!.

d E

5. '

L

{

1

)

1 pr4rg go t) n%I %E2?.T. E!CD Amendment No. M, 128 164d-

---

_____.__.m_

____________l,_____