ML19242D151
| ML19242D151 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/06/1979 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19242D148 | List: |
| References | |
| NUDOCS 7908140556 | |
| Download: ML19242D151 (15) | |
Text
.
ESCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGES BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (DOCKET NOS, 50 259,50-26J, 50-296) 7908140ssc, 627316
UiIT ONE 627317
LIMITING COUDITIOIG FOR OPERATION SUTNEILIANCE REQUI tEMENT" 3.6.A Thermal and Pressurization 4.6.A Therml and Pressurization Limitations Limita tions y 3 Durin6 heatup by non-nuclear 3 Test specimens represent.ir# the means, except when the vessel reactor vessel, base weld,and weld is vented, cooldown following heat affected zone metal shall be nuclear shutdown on low-level installed in the reactor vessel physics tests,the reactor adjacent to the vessel vall at vessel temperatures shaL1 be the core midplane level. The at or above the temperatures number and type of specinens of curve #2 of figure 3.6-1. vill be in accordance C tn SE report IEDO-10ll$. ne specimens chall meet the intent of ASTM E 185-70. Samples shall be with-drawn at one-fourth and three-fourths service life.
- 4. De reactor vessel shell 4. Neutron flux vires shall te '_a-temperatures during inservice stalled in the reactor v:asel hydrostatic or leak testing aljacent to the reacLar vessel shall be at or above the vall at the cor emid;) lane level.
temperatures shown on curve ne vires shall be recoved and
- 1 of figure 3.6-1. tested during the first refueling outage to experimentally verify
- 5. The reactor vessel head bolting the calculated values of neutror, studs may be partially fluence at one-fourth of the tensioned (four sequences of beltline shell thickness that the seating pass) provided the are used to determine the :a n studs and flange materials are shift from Figure 3.b- 2 .
above 70*F. Before loading the g 5,
flanges any more, the vessel bolting studs are tensioned and flange and head flange must be the reactor is in a cola :s r.ds -
greater than 100 F, and must tion, the reactor vesse. ncLL remain above 100*F while under temperature immediately cciov full tension. the head flange shall be per-manently recorded.
- 6. Be pump in an idle recircula- 6. Prior to and during startup of tion loop shall not be started an idle recirculation loop, t r.e unless the temperstures of the temperature of the reacter ecol-coolant vithin the idle and ant in the operating anc. idle operating recirculation loops loops shall be permanently are within 50 F of each other. logged.
- 7. ne reactor recirculation pumps 7. Prior to starting a recircu'.a-shall not be started unless the tion pump, the reactor conant coolant temperatures between temperatures in the dome and in the dome and the bottom head the bottom head drain shall be drnin are within 145 F. cocipared and pemanently lodded.
I 175 V
6C318
4 FICURE 3.6-1 CURVE #_1 Minimum temoma cc for presrare tests such as required by Section XI C
_URVE #2 Minimum temperature
/ggg for mechanical heat
, i,,, , up or cooldown
' ' ' 'W ' - following nuclear
, , ,'l'l. .M, / , , 2 i shutdown
. 3
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CURVE #3
/ OOC Minimum temperature i . i 4 i i / , ,
. < , for core operation l l i l', ,/ '
l'l ll' _ ( criticality) _
' Includes additional
,f ; ,
f i ii, / , , ,> e.ugin req'd by
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l'il,,l ,10CFR50 Appendix C ,
}= 800 l
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S g= 600 ,
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,
- i e i i i L , l I e i l 0 DO MO 300 400 MINIMUM TEMPERATURE *F ABOVE CHANGE IN TRANSITION TEMPERATUPI 188 627319
3.6/h.6 B "S EC 3.6.A/h.6.A The vessel pressurization temperatures at any time period can be determined f rom the thermal power output of the plant and its relation to the neutron flucnce and from figure 3.6-2. For heatup or cooldown and core operation, see curves #2 & #3 on figure 3.6-1. During the first fuel cycle, only calculated neutron fluence values can be used. At the first refueling, neutron dosimeter wires which are installed adjacent to t).e vessel vall can be removed to verify the calculated neutron fluence. As more experience is gained : cal-culating the fluence the need to verify it experimentally will disapper; Because of the many experinental points used to derive figure 3.6-2, there is no need to reverify if for technical reasons, but in case verification is required for other reasons, three sets of mechanical tect specinens repre-senting the base metal, w^ld metal and weld heat affected zone metal have been placed in the vessel. These can be removed and tested as required.
As described :n paragraph h.2.5 of the safety analysis report, detailed stress analyses have been made on the reactor vessel for b]th steady-state and transient conditions with respect to m.aterial fatigue. The results of these analyses are compared to allowab]e stress limits.
F.equiring the coolant temperature in an idle recirculation loop to be within 50 F of the operating loop temerature before a recirculaticn pump is started assures that the changes in coolant temperature at the reactor vessel nozzles and bottom hec i region are acceptable.
The coolant in the bottom of the vessel is at a lower temperaure thaa that in the 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 III limits when the temperature diff erential is not greater than lh5 F.
The requirements f or full tension boltup of the reactor vessel clesure are based on the NDT temperature plus 60*F. This is derived from the requirteents of the ASME code to which the vessel was built. The NDT temperature of the closure flanges, adjacent head, and shell =aterial is a maximum of 40*F and a maximum of 10*F for the stud caterial.
Therefore, the minimum temperature f or f ull tension boltup is 40*F plus 60*F for a total of 100*F. The partial boltup is restricted to tho full loading of eight studs at 70*F, which is stud NDT temperature (10*F) plus 60'F. The nyytron radiation fluence at tbs closure flanges is well below 10 nvt > 1 Mev; therefore, radiation effects a will be minor and will not influence this temperature.
3.6.B/h.6.E Coolant Chenistry
!Jat< -i,1s in the primarl systen are primarily 30h stainless steel and the Zirealoy cladding. The reactor water chemistry linits are established to prevent da. age to these materials. Limits are placed on condu:'172 y anc chloride concentrations. Conductivity is limited because it i; cont.i.au.w measured and gives an indication of abnornal conditiora c.C the presc..cc or unusual e.aterials in the coolant. Ch!cride limits are specified to p x/c.it stress corrosion cracking of stainless steel.
216 627320
4
- 8 UNIr TWO
,,3 r , .,
~
LIliITI!M C0f."dITIOrm FOR OPEPATIOil SUTNEILIANCE RFOTI IDCT
3.6.A 7termal and Pres urization 4.6.A Thermal and Pressurization Limitations Li raita t i ons v 3 During heatup by non-nuclear 3 Test specir: ens representing the means, except when the vessel reactor vessel, base r ld,and weld is vented, cooldovn following heat af fected zone taetal shall be nuclear shutdown on low-level instal _ led in the reac*ar vessel physics tests,the reactor adjacent to the vesset aail .it vessel temperatures shall be the core ctidplane level. Be at or above the temperatures number arid type of speci., er.s of curve 82 of figure 3.6-1. will be in accordance e m cc report NELO-10ll5. Le :.pecicens chall meet the intent of ASTM E 185-70. Suaplea chall be with-drawn at one-fourth an,i three-I fourths service life.
- 4. The reactor vessel shell 4. Neutron flux vires shall te in-
' empemtures during inservice stalled in the reactor ver.sel ttydrostatic or leak testing adjacent to the reacto. vessel shal) 't at or above the vull at the core midplane level.
temperatures shown on curve ne vires shall be renoved and
- 1 of figure 3.6-1 tested duzir.g the fir:,c refueling outage to experimentally ver fy
- 5. The reactor vessel hsad boltin.e the calculated values of neutron studs may be partially fluence at one-fourth of .he o t ensioned (four sequences of gg gg g g the seating pass) provided the are used to determine the FJI'T studs and flange - arials are e f e 34-2 above 70*F. Before loading the V flanges any more, the vessel 5 Whan the rmetor vessel head bolting studs are tensioned and flange and head flange must be the reactor is in a cold condi-greater than 100*F, and must tion, the reactor vessei nel1 remain above 100*F while under temperature ir: mediately celov rull tension. the head flange shall be per-manently recorded.
- 6. ne pump ir an i<i) e recircula- 6. Prior to and durind stcetu., of tion loop shall nut be started an idle recirculation loop, the unless the temperstures of the temperature of the reacter ecol-coolant within the idle and ant in the operatir.g an: idle operating recirculation loops leops shall be perr:anently are within 50 F of each other. logged.
- 7. m e reactor recirculation pumps 7 Prior to starting a recircula-shall not be started unles.c the tion pump, the reacter cocle.nt coolant temperatures between temperatures in the dome and in the dome and the bottom head the bottom head drain shall Le
- nin are within 145 F. ccepared and pc.manently logged.
i 175 V
Y.00?&
FICURE 3.6-1
.C_URVE #1 Minimum temperature for pressure tests such as required by Section XI CURVE #2 Minimum temperature fggg for mechanical heat Up Of coOldoVn
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l 0 DO 200 300 400 MINIMUM TEMPERATURE *F ABOVE CllANGE IN TRANSITION TEMPERATURE 188 W7323
~
3.6/h.6 BADE 3 3.6.A/h.6.A The vessel pressurization temperatures at any time period can be determined from the thermal power output of the plant and its relation to the neutron fluence and from figure 3.6-2. For heatup or cooldown and core operation, see curves #2 & #3 on figure 3.6-1. During the first fuel cycle, only calculsted neutron fluence values can be used. At the first refueling, neutron dosimeter wires which are installed adjacent to the vessel vall can be removed to verify the calculated neutron fluence. As more experience is gained in cal-culating the fluence the need to verify it experimentally will disappea .
Because of the many experinental points used to derive figure 3.6-2, there is no need to t everify if for technical reasons, but in case verification is required for other reasons, three sets of mechanical test specinens repre-senting the base metal, veld metal and veld heat affected zone metal have been placed in the vessel. These can be removed and tested as required.
As described in paragraph L.2.5 of the safety analysis report, detailed stress analyses have been made on the reactor vessel for bcth steady-state and transient conditions with respect to material fatigue. The results of these analyses are compared to allowable stress limits.
Requiring the coolant temperature in an idle recirculation loop to be within 50 F of the operating loop temerature before a recirculation pump is started assures that the changes in coolant temperature at the reactor vessel noszles and bottom head region cre acceptable.
The coolant in the bottom of the vessel is at a lower temperaure than that in the 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 III limits when the temperature differential is not greater than lh50F.
The cacuire=ents for full tension boltup of the reactor vessel closura ar,: L: sed on the NDT tecperature plus 60*F. This is derived from the requirements of the ASME code to which the vessel was built. The NDT temperature of the closure flanges, adjacent head, and shell material is a maximum of 40*F and a maximum of 10*F for the stad =aterial.
Therefcre, the minimum temperature for full tensica boltup is 40*F plus 60*F for a total of 100*F. The partial boltup is restricted to the full loading of eight studs at 70*F, which is stud NDT te=perature (10*F) plus 60*F. The nyytron radiation fluence at the closure flanges is well below 10 nyt > 1 Mev; therefore, radiation effects vill be minor and will not influence this ta=perature.
3.6.B/h.6 5 Coolant Chenistry Vat .ials in the prinary system are primarily 304 stainless steel and the Zircaloy cladding. The reactor water chemistry linits are estahl inheu to prevent danage to these materials. Limits are placed on cenduelIv; q and chloride concentrations. Conductivity in limited because it ja continoal; neasured end gives an indication of abnormal conlitioru and the prescnce of unusual naterials in the coolant. Ch!oride limits _re specified to >cevent stress corrosion cracking of stainless steel.
216 6U324
O e
UNIT THREE 607325
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RFQUIREMENTS
- l. 6 PHIMHY SYSTEM BOUNDARY 4.6 PRIMARY SYSTEM BCUNDARY 4 The reactor vessel 4 Neutron flux wires shell temperatures shall be installeG in during inservice the reactor vessel hydrostatic or leak adjacent to the testing shall be at reactor vessel wall or above the at the core midplane temperatures shown on level. The wires curve Number 1 of shall be removed and f igure 3.6-1. tested during the first refueling
- 5. The reactor vessel head outage to bolting studs may be experimentally verify partially tensioned the calculated values of integrated neutron (four sequences of the fluence of one-fourth seating pass) provided f the belt line the studs and flange shell thickness that materials are above #' " ' "
70*F. Before loadin8 the the NDTT shift from flanges any more, the Figure 3.6-2.
vessel flange and head 5. When the reactor flange must be greater vessel head bolting than 100*F, and must studs are tensioned remain above 100*F wht: 0 and the reactor is in under full tension. a cold Condition, the reactor vessel shell temperature immediately belcw the head flange shall be
- 6. The pump in an idle permanently recorded.
recirculation loop chall not be started 6. Prior to and during unless the startup of an idle temperatures of the recirculation loop, coolan t within the the temperature of idle and operating the reactor coolant recirculation loops in the operating and are within 500F of idle loops shall be each other. permanently loqqed.
7 The reactor 7. Prior to starting a recirculation pumps recirculation pump, shall not be started the reactor coolant unless the coolant temperatures in the temperatures between dome and in the the dome and bottom bottom head drain head drain are within shall be compared and 1450F, permanently lcqged.
r.
h.,,,-.,g.,D p., /Le M
FICURE 3.6-1 CURVE #1 Minimum temperature for pressure tests such as required by Section XI CURVE #2
-Minimum temperature
/POC ,
~
- for mechanical heat
_ _ . I i i ,
i Up Or cooldown W '- following nuclear
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CURVE #3
/000 ,
_ Minimum temperature i
e 1
.f i , for core operation ll i ,
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g l,l '
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,= 800 .
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I i i i O DO MO 300 400 MINIMUM TEMPERATURE *F ABOVE Cl!ANGE IN TRANSITION TEMPERATUPI 2 0
. a . n. . awt 8 . adP d
3.6/4.6 BASES O
r thercul power output if no great changes in core geometry are made.
The vessel pressurization temperatures at any time period can be determined from the thermal power output of the plant and its relation to the neutron fluence and from figure 3.6-2. For heatup or cooldown and core operation, see curves 82 G #3 on figure 3.6-1. During the first fuel cycle, only calculated
. neutron fluence values can be used. At the first refueling,
. -" a neutron docimeter wires which are installed adjacent to the
^~ '
vessel wall can be removed to verify the calculated neutren fluence. An more experience is gained in calculating the fluence the need to verify it experimentally will disappear. Because of the many experimental points used to derive figure 3.6-2, there is no need to reverify if for technical reasons, but in case verification is required for other reasons, three sets of mechanical test specimens representing the base metal, weld metal
.. and weld heat aff ected zone metal have been placed in the vessel.
These can be removed and tested as required.
As described in paragraph 4.2.5 of the saf ety analysis report, detailed stress analyses have been made on the reactor vessel for both steady-ctate and transient conditions with respect to y material fatigue. The results of these analyses are compared to allowable stress limits. Requiring the coolant temperature in an (( ')
idle recirculation loop to be within 500F of the operating loop temperature before a recirculation pump is started assures that the changes in coolant temperature at the reactor vessel nozzles and botton head region are acceptable.
The coolant in the bottom of the vessel is at a lower tempt:rature than that in the upper regions of the vessel when there is no recirculation flow. This colder water is forced up when recirculation pumps are started. This wi'.1 not result in stresses which exceed ASME Boiler and Pressure vessel Code,Section III limits when the temperature differential is not greater than 1450F.
The requirements for full tension boltup of the reactor vessel closure are based on the NDT temperature plus 60*F. This is derived from the requirements of the ASME code to which the vessel was built. The NDT temperature of the closure flanges, adjacent head, and shell material is a maximum of 40*F and a maximum of 10*F for the stud material.
Therefore, the minimum temperature for full tension boltup is 40*F plus 60*F for a total of 100'F. The partial boltup is restricted to the f ull loading of eight studs at 70*F, which is stud NDT temperature (10*F) plus 60'F. The ng tron radiation fluence at the closure flanges is well below 10 nyt ?,1 Mev; therefore, radiation effects will be minor and will not influence this temperature.
O e
ENCLOSURE 2 627329
- 1. Proposed Revision to Specification 3.6.A.5 The General Electric Company (GE) has determined that the closure flanges may be preloaded by partial bolt tensioning (either eight bolts under full tension or a greater number of bolts under partial tension to give equivalent loading) in order to seat and seal the 0-rings at a temperature of 70*F (Reference 1). Because of the sequence of the boltup procedure, the head seating passes will result in loading the bolts and flanges to meet the above restriction.
This change is allowed based on the fact that the stress imposed by partial tensioning is far less than the stress imposed on the flanges by full bolt tensioning. Therefore, at partial tension the limiting factor is the stud NDT which is 10'F. For fracture toughness, the rcquired 60*F safety f actor is added to the stud NDT which results in the 70*F restriction on this partial tensioning. As reflected by technical specification Figure 3.6-1, the boltup temperature above this partial tensioning is 100*F minimum.
- 2. Proposed Revision to Figure 3.6-1 GE Topical Report NEDO-21778, " Transient Pressure Rises Af fecting Fracture Toughness Requirements for Boiling Water Reactors," was prepared and submitted for NRC review to provide justification for modifying the requirements for the minimum permissible temperature of the reactor pressure vessel when the core is critical as set forth in paragraph IV.A.2.c of 10 CFR 50, Appendig G. In the topical report evaluation, provided as enclosure to letter from Olan D. Parr to Dr. G. G. Sherwood dated November 13, 1978, the NRC staff agreed with the requested deletion of the criticality limit based on the minimum permissible temperature for the inservice hydrotest.
This revision will allow nuclear heat to be utilized above 100*F and will decrease vessel heatup time. NEDO-21778 and the topical report evaluation provide the necessary justification for this revision to Figure 3.6-1.
W47330