ML20115G036

Amend 155 to License DPR-46,revising TS to Validate Existing Pressure Vs Temp Operating Limit Curves

ML20115G036
Person / Time
Site:	Cooper
Issue date:	10/13/1992
From:	Bevan R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20115G040	List: ML20115G036 ML20115G041
References
NUDOCS 9210230322
Download: ML20115G036 (10)

Text

t pS RIG

+

o, UNITED STATES 8

', m '

,n NUCLE AR REGULATORY COMMISSION h

'E WASHINGTON, D. C, 20555 o

%...../

NEBRASKA PUBLIC POWFR DISTRICT

@CKET NO. 50-298 COOPER NUCLEAR STATION MEBDMENT TO FAfillTY OPERATING LICENSE Amendment No. 155 License No. DPR-46 1.

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

A.

The aoplication for amendment by Nebraska Phlic Power District (the licensee) dated July 28, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i

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 Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the l

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.

1 9210230322 921013 PDR ADOCK 05000298 P

PDR

P

3-i 2.

Accordingly, the license is amended by changes to the Technical Specifi-4 cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:

2.

Technical Soecifications i

l The' Technical Specifications contained in Appendix A, as revised i

through Amendment No.155,- are hereby incorporated in the license.-

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

i l

FOR THE 7UCLEAR REGULATORY COMMISSION

-John T. Larkins, Director Project Directorate IV-1 Division of-Reactor Projects - III/IV/V j

Office of Nuclear. Reactor Regulation L i

Attachment:

Changes to the Technical Specifications i

j.

Date of Issuance:

October 13, 1992 t

i 0

e i

d r

4

---sve y

r p -.,,,

-r-,<

, *, ~,,w!:,

,m-,,,wc-w,w,

,,w.a.,,w.,.,,.,wr.yq-=4.,,y,w,,,

,.-g, e--.,,.,

-pi,y,,-emv ed T

1;-

1 i

ATTACHMENT TO L' CENSE-AMENDMENT NO. 155 i

j-FACILITY OPERATING LICENSE NO. DPR-46 DOCKET N0' 50-298 L

1 i

i Replace the following pages of the Appendix A Technical Specifications with i

the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

v 4

l-REMOVE PAGES INSERT PAGES.

i 132 132 133-133 i-147-147 1

l 154 154

(

}

155 155 l.

156

'156 1

i i

157 157-158 158 g

1 i-f s

o

?

i' i.

p g,

j

=

n.

f., '

i i

$I' i

i f.'.

.,.......,.m..

,,.... ~ ~

,..., _,., _ _,...,,,,. _,, ~,,,...

LIMIT;NC CONDITIONS FOR OPEPATION SUPNEILLANCE REOUTREM.ENTS 3.6 Primary System Boundarv 4.6 Primary System Boundary Aeolicability:

Applicability:

Applies to the operating status of Applies to the periodic examination

~

the reactor coolant system.

and testing requirements for the reactor cooling system.

Obiective:

Obiective:

I To assure the integrity and safe To determine the condition of the operation of the reactor coolant reactor coolant system and the system.

operation uf the safety devices related to it.

Enecification:

Specification:

A, Thermal ani, Pressurization A.

Thermal and Pressurization Limitations Limitations 1.

The average rate of reactor coolant 1.

During heatups and cooldowns, the temperature change during normal following temperatures shall be heatup or cooldown shall not exceed permanently logged at least every 100'F/hr when averaged over a

15 minutes until the difference one hour period, between any two readings taken over a 45 minute period is less than 50*F.

a.

Bottom head drain.

b.

Recirculation loops A and B.

2.

During operation where the core is 2.

Reactor vessel temperature and critical or during heatup by reactor coolant

• pressure shall be nonnuclear means or cooldown permanently logged at least every following

shutdown, the reactor 15 minutes whenever the shell vessel metal and fluid temperatures temperature is below 220*F and the shall be at or above the reactor vessel iv not vented, temperatures shown on the limiting curves of Figures 3.6.1.a or 3.6.1.b.

This specification applies when the reactor vessel head is tensioned.

I 3.

The reactor vessel metal 3.

Test specimens of the reactnr vessel temperatures for the botton head base, weld and heat affected zone reginn and beltline region shall be metal subjected to the highest at or above the temperatures shoc fluence of greater than 1 Mav on the limiting curves or neutrons shall be installed in t Figure 3.6.2 during inservice reactor vessel adj acent to e

hydrostatic or leak testing.

The vessel vall at the core midpla...

Adjusted Reference Temperature (ART) level.

The specimens and sample for the beltline region must be program shall conform to ASTM determined from the appropriate E 185-73 to the degrc^ possible.

l beltline curve (13, 18, or 21 EFPY) depending on the current accumulated i-number of effective full power years (EFPY).

Amendment No. Z20.155

132,

+

l 11MITINc CONDITIONS rop OPrgATION S17tVEILI).NCE REQUIRD4ENTS 3.6.A (cont'd.)

4.6.A (cont'd.)

The reactor vessel surveillance specimens shall be removed and examined to determine changes in their material properties as required by 10 CFR 50 Appendix H.

4.

The Reactor vessel head bolting 4

When the reactor vessel head bolting studs shall not be under tensior.

studs are. tensioned and the reactor unless the temperature of the vessel is in a Cold Condition, the reactor head flange and the head is greater vessel shell temperature immediately tt m 80'T.

below the head flange shall be pemanently recorded.

5.

The pump in an idle recirculation 5,

Prior to and during startup of an loop shall not be started unless the idle recirculation

loop, the temperatures of the coolant within temperature of the reactor coolant the idle and operating recirculation in the operating and idle loops loops are within 50'r of each other.

shall be permanently logged.

6.

The reactor recirculation pumps 6.

Prior to starting a recirculation shall not be started unless the

pump, the reactor coolant coolant temperatures between the temperatures in the dome and in the dome and. the bottom head drain are bottom head drain-shall be compared within 145'F.

and permanently logged.

i i

l 1

133 Amendment No. 120, 155

-j

3.6. A 6 4.6. A RMD (cont'd)

As described in the saiety analysis report, detailed stress analyses have been made on the reactor vessel for both steady state and transient conditions with respect to material fatigue.

The results of these analyses are compared to allowable stress IImits.

Requiring $0'F ofthe coolant temperature in an idle recirculation loop to be within the operating loep temperature before a recirculation pump is started assures that the changes in coolant temperature at the reactor vessel nozzles and bottom hud region are acceptable.

The coolant in the bottom of the vessel is at a lower temperature than that in toe upper regions of the vessel when there is no recirculation flow.

This colder water is forced up when recirculation pumps are started.

This will not result in stresses which exceed ASME Boiler and Pressure Vessel Code, Section 111 limits when the temperature differential is not greater than 143'F.

The first surveillance capsule was removed at 6.8 EFPY of operation and base metal, weld metal and HAZ specimens were teste'd.

In addition, flux vires were tested to experimentally determine the integrated neutron flux (fluence) at the surveillance capsule location.

The test rer%1ts are presented in General Electric Report MDE.103 0986.

Measured shifts in RTer of the base metal and weld metal were compared to predicted values per Regulatory Guide 1.99, Revision 1 which was in effect at that time.

The measured values were higher than nredicted, so the 1.99 methods were modified to reflect the surveillance data. The test results for the flux wires were used with analytically determined lead factors to determine the peak end of life {EOL) fluence at the 14 T Vessel wall degth.n/cm]he value corresponding to 0 years operation (3 EFPY) is 1.5 x 10 Subsequent to this evaluation, the NRC issued Regulatory Guide 1.99, Revision 2.

This revision requires that two surveillance capsules be tested before the test results are factored into the adjusted reference temperature (ART) shift predictions.

The adjusted reference temperature of a beltline material is defined as the initial RT lus the RT"nitial due develope 77from to irradiation.

Therefore, the curves the 1 surveillance capsule testing were re evaluated in accordance with the guidance provided in Regulatory Guide 1.99 Revision 2.

Based strictly on the chemistry factors provided in Regulatory Guide 1.99 Revision 2, and considering each beltline material chemistry and peak fiuence at a given ETPY, the pressure temperature curves in Figures 3.6.1.a and 3.6.1.b, which reflect a beltline ART of 110'F, were determined to be valid for 21 EFPY.

Figure 3.6.2, the pressure test curve,21 ETPY was re evaluated in like includes curves for-13, 18 and to provide more manner and flexibility in pressure testing.

Figure 3.6.2 also has a separate curve for the bottom head region.

'the bottom head curve does not shift with increased operation; therefore, the bottom head tewperature can be I

monitored against lower temperature requirements than the beltline during pressure testing.

The surveillance capsule withdrawal schedule for the i

remaining specimens is located in Section IV.2.7 of the CNa USAR.

l B.

Coolant Chemistry Materials it. the primary sysi.em are primarily Type 304 stainless steel and Ziracloy cladding. The reactor water chemistry limits are established to provide an environment favorable to these materials. Limits are placed on conductivity and chloride concentrations. Conductivity is limited because it can be continuously and reliably measured and gives an indication of abnormal conditions and the presence of unusual materials in the coolant.

Chloride limits are specified to prevent stress. corrosion cracking of stainless steel.

Several investigations have shown that in neutral solutions some oxygen ia required to cause stress corrosion cracking of stainless steel, whfle in the absence of oxygen no cracki One of these is the chloride-oxygen relationshlp of Williamsb,g occurs.where it is shown that at high chloride concentration little oxygen is required to cause stress corrosion cracking of stainless steel, and at high oxygen concentration little chloride is required to cause cracking. These measurements were determined in a wetting and drying situation using al taline phosphate treated boiler water and therefore are of limited signi icance to BVR conditions. They are, however, a qua,litative indication (" rrends.

IV. L. Williams, Corrosion 13, 1957, p. 539t.

147 Amendment No. I20,155

l 1500 f

l g

muo To : uPy

/

8 1

1400 1

Adjusted Beltline 1/47 FLAW. ART e 110'F i;

1200 I

l-s i

1000 i

e r.00

/-

s i

F l

E e

}

I 600 f

l

$AFE OPERATING 400 REGION u

. NON-htLTLINE

[

FW N0ZZLE LIMITS, li4T FLAW, RTNDt*30'r l

200 i

/

SOLT PRELOAD TIM *f RATURE = 80*F FLANGI REGION l

RTNOT

• 20*F O

l 0

100 200-300 l

MwMUM visstL METAL TEMPERATunt teri l

j Tigure 3.6.1.a-M.inimum Temperature for Non-Nuclear Beatup or' Core Cooldown i

Tollowing Nuclear Shutdown -

154.-

Amendment No. 220. 155

~. -

a---.

~

e I

1600 g

VAUD TD fl EFFT C

1400 7

ADJUSTED SEC1NE.

1/47 FLAW. ART = 110'F 1200 1000

??

• S-k 5

g 800 g

E 3

600 es0N-444Jums SAFE PW se022LE UM4TS CPERATING PLUS 40'P. lief PLAW RE 310N ATNOT*30*F 400 REDUIRED IN IV.A.3, 10CFR60. APPEND!! E FLANGE REGION RTNOT*20;

MINIMUM PERMISSIBLE j

I

,00-

• TEMPERATURE = 80'F

, f PER 10CFR$0 r

APPENDIX G 0

0 t00 200 300 MINIMUM VESSEL METAL TEMPERATURE ('F)

Figure 3.6.1.b tiini=u:n Temperature for Core operation (Critica11:y) -

Includes 40CF Margin Required by 10CTR$0-Appendix G

)

155 Amendment No. 220, 155

- = -

k j

im l

i SOTTOM EFPY HEAD

~~

REGION IS 18 21 i

/

/ / /

/

/ / /

/

/ / /

/

/ / /

j j j j l

ll l

% DELTUNE CURVi$.

f f

f 1/4 7 8 LAW,

)

I ADJUSTED AS 1

j 1000

+-

f

ggown, i

F EFPY' ART l'Fi

/

H /

Ai

~

/

///

c' 800 SAFE i

E

[

/ [

OPEMTING REGION

/r l

- /N M

c" 1

y 1

.- 1 10* F

/

l 400 3

312 pass s

! \\

200 EOLT PRILOAD TEMPERATURE = 80'F

> FLANGE REGION l

j/ RTNDT " 20*F I

O o

100 200 300 MINIMUM VESSEL METAL TEMPERATURE t'FI Tigur 3.6.2 Minimum Temperature for Pressure Tests Such as Required by l

Section XI 156 Amendment No. 120, 155

t t

"INTENTIOllALLY LETT BLANK" J

d 3

l i

-157, 158.-

Amendment No, jgg, 355

...