ML20153G027
| ML20153G027 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/26/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20153G031 | List: |
| References | |
| NUDOCS 8805110121 | |
| Download: ML20153G027 (10) | |
Text
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/pa "%,h UNIVED STATES l'
?(
i NUCLE AR REGULATORY COMMISSION j
W ASHING TON, D. C. 20555
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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENCMENT TO FACILITY OPERATING LICENSE Amendment No.120 License No. DPR-46 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for anendment by Nebraska Public Power District (the licensee) datad October 28, 1987, and modified by letter dated February 22, 1988, complies with the standards and require-ments 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 confomity with the application, as amended, the provisions of the Act, and the rules and regulations of the Conmission; C.
There is reasonable assurance:
(i) that the activities autSorized 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 license amendment will not be inimical to the comon defense end security or to the health and 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.
8805110121 880426 PDR ADOCK 050002 4 P
2.
Accordinaly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(?) of Facility Operating it 9nse No. OPR-46 is hereby amended to read as follows:
2.
Technical Specifications
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The Technical Specifications contained in Appendix A, as revised through Amendment No.120, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications, j
3.
The license amendment is affective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1
9 C.
(< A H
{p'
/ Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Char.ges to the Technical Specifications Date of Issuance: April 26,1988
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ATTACHMENT TO LICENSE AMENDMENT NO.120 FACILITY OPERATING LICENSE NO. DPR-46 j
i DOCKET NO. 50-298 i
Replace the following paces of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
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132
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-133 i
l 136 147 154 155 156 157 l
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i LIM 2T2NG' COND2TZONS FOR OPERAT20N SURVE8LLANCE REQU2REMENTS
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3.6 Primary System Boundary 4.6 Primary System Boundary Applicability:
Applicability:
Applies to the operating status of Applies to the periodic examination the reacter coolant system.
and testing requirements for the reactor cooling system.
j Objective:
Objective:
To assure the integrity and safe op-To determine the condition of the eration of the reactor coolant sys-reactor coolant system and the operation of the safety devices tem.
reisted to it.
i Specification:
Specification:
A.
Iharmal and Pressurization Limitatf ons A.
Thermal and Pressurization Limitations 1.
The average rate of reactor coolant 1.
During heatups and cooldowns, the temperature change during normal heat-following temperatures shall be per-up or cooldown shall not axceed manently logged at least every 15 100*F/hr when averaged over a one-minutes until the difference between hour period.
any two readings taken over a 45 minute period is less than 50'F.
4 a.
Bottom head drain, b.
Recirculation loops A and B.
2.
During operation where the core is 2.
Reactor vessel tarperature and reactor critical or during heatup by non-coolant pressure shall be permanently nuclear means or cooldown following logged at least every 15 minutes when-i snutdown, the reactor vessel metal ever the shell temperature is below and fluid temperatures shall be at 220*F and the reactor vessel is not or abov a the temperatures shown vented.
on ths limiting curves of Fig-ures 3.6.1.a or 3.6.1.b.
3.
The reactor vessel metal tenparatures for the botton head region and beltline region shall be at or above 3.
Test specimens of the reactor vessel the temperatures shown on the base, veld and hea t aff ected zone metal ilmiting c'trves of Figure 3.6.2 subjected to the tighest fluence of during inservice hydrostatic or leat greater than 1 Mes neutrons shall be testing. The Adjusted Reference installed in the reactor vessel ad' scent Temperature (ART) for the beltline to the vessel wall at the core midplane region must be determined from the level. The specimens and sample program appropriate beltline curve (8,10, shall conform to ASTM E 185-73 to i
or 12 EFPY) depending on the current the degree possible, accumulated number of effective full 1
power years (EFPY).
The ART curve for the bottom head is valid to
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12 ETPY, Amendment No.120
-132-
LIMIT 8NG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS i
3.6.A (cont'd.)
4.6.A (cont'd.)
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The schedule for withdrasal of the remaining two capsules is based on ASTM E185-82 and is as follows:
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Second Capsule:
15 ETPY l
Third Capsules,32 EFPY s
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4 The Reactor vessel head bolting 4.
When the reactor vessel head bolting studs shall not be under tension studs are tensioned and the reactor is unless the temperature of the vessel in a Cold Condition, the reactor vessel i
head flange and the head is greater shcil tezparature Lamediately below than 60 F.
the head flange shall be permanently l
recorded.
1 5.
The pump in an idle recirculation loop 5.
Prior to and during startup of an shall not be started unless the temp-idle recirculation loop, the temperature i
eratures of the coolant within the of the reactor coolant in the operating idle and opergting recirculation loops and idle loops shall be permanently are within 50 F of each other.
logged.
6.
The reactor recirculation pumps shall 6.
Prior to starting a recirculation pump.
not be started unless the coolant the reactor coolant temperatures in te=peraturesbetweenthedomeangthe the dome and in the bottom head drain bottom head drain are within 145 F.
shall be compared and permanently logged.
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-133-Amendment No.120
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v 3.6.A &'4.6.A BASES
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Thermal and Pressurization Limitations The requirements for the reactor vessel have been identified by evaluating.the need for its integrity over the full spectrum of plant conditions and events.
This is accomplished through the Station Nuclear Safety Operational Analysis (Appendix G) and a detailed functional analysis of the reactor vessel.
The limits expressed in the technical specification for the applicable operating stares are taken from the actual Nuclear Safety Operational Requirements for the reactor vessel as given in Subsection IV-2.8 of the Updated Safety Analysis Report.
The components of the nuElear system pressure bounds.ry are constructed so that its initial maximum nil-ductility transition temperature (RT NDT) is not greater than 40'F. as cited in Subsection IV-2.5 of the Updated Safety Analysis Report.
l The heatup-cooldown and hydrostatic test minimum pressurization temperatures were calculated to comply with the recommendations of Appendix G of Section III.
ASME 3 oiler and Pressure Vessel Code 1972 Summer Addendua.
The temperature versus pressure limits when critical which are presented in Figure 3.6.1.b assure compliance with Appendix G of 10CFR50.
Tightening the studs on the reactor vessel head flexes it slightly to bring together the entire contact surfaces adjacent to the 0-rings of the head and vessel flange. The reactor vessel head flange and head are constructed so that their initial maximus NDIT is 20*F, as cited in Paragraph IV-2.5 of the Updated Safety Analysis Report. Therefore, the initial minimum temperature at l
which the studs can be placed in tension is established at 80*F (20'T + 60'F).
The total integrated neutron flux in the head glange rggion will be less than that at the core mid-plane level by a factor of 10~ or 10'. therefore, eg9 maximum calculated fluence in the head flange region will be far belov 1 x 10 nyt.
With such a low total integrated neutron flux in the head flange region, there will be no detectable or significant NDTT shif t, and the minimum stud tightening temperature remains at 80'F.
The reactor vessel is designed in accordance with the ASME Boiler and Pressure Vessel Code, Section 111. for a pressure of 1250 psig. The pressure limit of 1035 psig represents the maximum expected operating pressure in the steam dome when the station is operating at design thermal power. Observation of this limit assures that the operator remains within the envelope of conditions considered by Chapter 14 of the Updated Safety Analysis Report.
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 limits. The specific conditions analyzed included a maximum of 120 cycles of normal startup and shutdown with a heating and cooling rate of 100'T per hour applied continuously over a temp-erature ranga of 100'T to 546*F.
The expected number of normal heacup and cool-down cy.:les to which the vessel will be subjected is 80.
-146-Amendment No.120
3.6.A 6'4.6.A, BASES (cont'd)
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As described in the safety 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 limits. Requirgnsthecoolanttemperatureinanidlere-circulation loop to be within 50 F of the operating loop temperature before a recirculation pump is started assures that the changes in coolant temperature at the reactor vessel nozzles and bottom head region are acceptable.
The coolant in the bottom of the vessel is at a lower temperature than that in the upper regions of the vessel when there is no recirculation flow. This i
colder water is forced up when recirculation pumps are started. This will not
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result in stresses which exceed ASME Boiler and Pressure Vessel Code 3 Section III limits when the temperature differential is not greater than 145 F.
The first surveillance capeule was removed at 6.8 EFPY of operation and base metal, veld metal and HAZ specimens were tested.
In addition, flux vires were tested to experimentally determine the integrated neutron flux (fluence) at the surveillance capsule location. The test results are presented in General Electric Report MDE-103-0986. Measured shifts in RT of the base metal and weld metal 1
i were compared to predicted values per RegulaEry Guida 1.99, Revision 1.
The measured values were higher than predicted, so the 1.99 methods were modified to reflect the surveillance data. The test results for the flux vires were used with analytically determined lead factors to determine ths peak end-of-life (EOL) fluence at the 1/4 T Vessel wa1 depch The value corresponding to 40 years operation (32EFPY)is1.5x10{8 n/cm The adjusted reference temperature (ART) of a beltline material is defined as I
the initial RT plus the RT shif t due to irradiation. The curves of Figures 3.6.1.Nnd3.6.1.brIEectabeltlineARTof110'F,makingthemvalidfor operation up to 12 ETPY. Figure 3.6.2, the pressure test curve, includes curves d
with ART values for 8,10 and 12 EFPY to provide more flexibility in pressure testing. Figure 3.6.2 also has a separate curve for the bottom head region. The bottom head curve does not shif t with increased operation. Therefore, the bottom I
head temperature can be monitored against lower temperature requirements than the beltline during pressure testing, i
B.
Coolant Chemistry 3
Matsrials in the primary system are primarily Type-304 stainless steel and Ziracioy cladding. The reactor water chemistry limits are established to provide an environment favorsble to these materials.
Limits are placed on conductivity and chloride concentrations. Conductivity is limited because it can be continuously j
and reliably measured and gives an indication of abnormal conditions and the 1
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 is i
required to cause stress corrosion cracking of stainless steel, while in the absence of oxygen no cragking occurs. One of these is the chloride-oxygen relationship of Williams, where it is shown that at high chloride concentration 4
little oxygen is required to cause stress corrosion cracking of stainless steel.
and at high oxygen co uentration little chloride is required to cause cracking.
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These measurements were determined in a vetting and drying situation using j
alkaline-phosphate-treated boiler water and therefore, are of limited significance to BWR conditions. They are, however, a qualitative indication of trends.
I V.J.. Williams, Corrosion 13, 1957, p. 539t.
-147-Onendment No,120
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-154-Amendment No.120 J
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I 1800 l
l VAu0 TO 12 EPPY t
1400 i
Adjusced Beltline ll4T FL.AW, ART.1 to*F r
1200 s
1000 2
800 3
o 600 SAFE OPERATING REG 4CN
'OO 1
NON 8tLTUNg FW NCZ2Lf LIMaTS.
o 1s47 FuW. RTsoy.3c r 200
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SCLT PRILOAD TEMPE RATumt. G O* F i
FLANGE REGION RTuo7 20*F i
0 O
100 200 3go MINIMUM Vi$$(L METAL TEMP (RATUR( ('pg 4
Tigur$ 3.6.1.a Minimum Temperature for Non-Nuclear Heatup or Core Cooldown Following Nuclear, Shutdown 155 feendment No,120
1400 l
VAUD TO 12 IFPY C
i 1400 t
Adjusted Beltline 1t47 FLAW, ART = 110'F 1200 l
tc00 1
!E 800 I
w a
400 NON-BILTLtNU SAft FW NOZZLt LIVITS OPERATING PLUS 40*F,114T FLAW REGION 0
RTgoy = 30 7 400 FLANGE REGION RTNOT
- 20*F; MINIMUM PfAMIS$telt 200
" TEMPtRATURE = 80'F
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Pim 10CFR50 APPENDtX Q a
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100 200 300 MINIMUM VESSEL METAL TEMPERATURE L'F) l r
7}gure 3.6.1.b tiinimum Temperature for Core operation (Criticality)
Includes 400T Margin Required by.10CTK50 Appendix C t
Amendment No. 120 gg
1600 BOTTOM IFPY 1
HEAD REGION 8 10 12
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ADJUSTED AS J
1000 1
SHOWN:
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600 f
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400 I
312 peg s l
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SOLT PetLOAD l
l 200 TEMPERATURE = 80*F J
' FLANGE REGION
[ RTuoy=20'F j
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o 100 200 300 MINIMVM VLSSEL METAL TEMPERATURL L'F)
Figure 3.6.2 Minit:um Temperature for Pressure Tests Such as Required by Section XI o
157 Amendment No.120
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