ML20137F563

Proposed Tech Specs Re Reactor Pressure Vessel Test Specimens & Temp & Pressure Limits for Pressure Tests

ML20137F563
Person / Time
Site:	Hatch
Issue date:	01/07/1986
From:	GEORGIA POWER CO.
To:
Shared Package
ML20137F549	List: ML20137F543 ML20137F563
References
TAC-60542, NUDOCS 8601170551
Download: ML20137F563 (9)

Text

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Y LIMITING (DtOITIONS FOR OPERATION SURVEILLANCE REQUIRDDTIS 3.6 PRDERY-SETEM BOUtOARY 4.6 PRIMARY SETEM BOUNDARY Applicability Applicability h Limiting Conditions for %e atrveillance Dentirements apply

. Operation apply to the oper- to the periodic examination and ating status'of the reactor testing reatirements for the coolant system. reactor coolant system.

[ . Objective Obiective -

!- h e objective of the Limiting h e objective of the atrueillance conditions for Operation is to Rentirements is to determine the asaire the integrity and safe condition of the reactor coolant

.-operation of the reactor coolant system and the operation of the

_aystem. safety devices related to it.

Specifications ~ Specifications A. Reactor Coolant-Heat'-Up and A. Reactor Coolant Heat-Up and Cooldown Cooldown

% e average rate of reactor h e reactor coolant system coolant temperature change temperature and presaire daring normal heatup or cool- shall be determined to be '

down'shall not exceed 100'F/hr within the limits of when averaged over a one-hair Specifications 3.6.A. and 3.6.B.

period. at least once every 30 mimtes diring reactor coolant heatup and cooldown.

B. Reactor Vessel Temperature and B. Reactor Vessel Tenparature and Presaire Presaire i

1.  % e reactor vessel shell temper- l Reactor vessel metal tenperature atures daring inservice hydro- at the altside airface of the static or leak testing shall be bottom head in the vicinity of at or above the tenperatures o the control rod drive batising shown on the alrve of Figttre 3.6-1. and reactor vessel shell adjacent to shell flange shall be re-corded at least every 15 4

mimtes d1 ring in-service hydrostatic or leak testing when i the vessel presaire is>312

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l Psig.

gii Og Sg[ j P PDR 1 HMG - UNIT 1 3.6-1

LIMITING (DtOITIONS FOR OPERATION SURVEILLANCE REQJIRDENIS 3.6.B. Reactor Vessel Temperature and 4.6.B. Reactor Vessel Temperature and Presaire (Contimed) Presaire (Contimed)

2. Daring heatup by non-mclear .

l Test specimens representing the means, cooldown following mclear reactor vessel, base weld and weld shatdown or low level physics tests,- heat affected zone metal were l the reactor vessel shell and fluid installed in the reactor vessel tenperatures of Specification 4.6.A. adjacent to the vessel wall at shall be at or above the tenperatures the core midplane level before shown on the curve of Figure 3.6-2. the start of operation. %e rumber and type of specimens are

3. D2 ring all operation with a critical l in accordance with GE report oore, other than for low level physics NEDO-10ll5. % e specimens meet tests, the reactor vessel shell and the intent of AS'IM E185-70.

fluid temperatures of Specification 4.6.A. shall be at or above the temper - The next airveillance capa11e

, atures shown on the curve of shall be removed from the ves-4 Figure 3.6-3. .

sel at approximacely 15 EFPY of operation, as reconne:~ led in AS'IM E185-82, b2t not to exceed 16 EFPY.

3.6.C. Reactor Vesr,el Head Stud C. Reactor Vessel Head Stud Tensioning Tensioning

% e reactor vessel head bolting When the reactor vessel head studs shall not be under tension studs are under tensfon and the unless the temperature of the reactor is in the Gold Stutdown vessel head flange and the head Condition, the reactor vessel is greater than 76'F. '

I shell temperature innediately below the henil flange shall be permanently recorded. .

D. Idle Recirculation Icop Si.3rtup D. Idle Reciro21ation Inop Startup me punp in an idle recirculation Prior to and cliting startup of an loop shall not be started unless idle reciraalation loop, the tem-the tenperatures of the coolant perature of the reactor coolant within the idle and operating re- in the operating and idle loop circulation loops are within 50*F shall be compared and permanently of each other. recorded.

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HA'IUI - UNIT 1 3.6-2

l BASES EOR LIMITING CDNDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMEN'IS A. Reactor Coolant Heatup and Cooldown he vessel has been analyzed for stresses calsed by thermal and pressure transients. Heating and cooling transients thrcughout plant life at uniform rates of 1000F per hour were consMered in the temperature range of 100 to 5460F and were shown to be within the realirements for stress intensity and fatigue limits of Section III of the ASME Boiler and Pressure Vessel Code (1965 Edition including Winter 1966 addenda) .

B. Reactor Vessel Temperature and Presmre Operating limits for the reactor vessel presaire and temperature I d1 ring normal heatup and cooldown, and daring inservice hydro-static and leak testing were established using 10CFR50 Appendix G, May 1983 and Appendix G of the Winter 1984 Addenda to Section III of the ASME Boiler and Pressure Vessel Code. In addition, operat-ing limits reflecting discontimity effects were calculated by adjusting BWR/6 discontimity analyses to reflect the appropriate Hatch 1 RTgyp values. 'Ibgether, these operating limits asaire that a postulated surface flaw, having a depth of 0.24 inch at the flange-to-vessel junction and one-cparter of the material thickness at all other reactor vessel locations can be safely acconmodated.

For the parpose of setting these operating limits, the RTgyp of the vessel material was estimated from impact test data taken in accordance with realirements of the Code to which this vessel was designed and mamfactured (1965 Edition including Winter 1966 Addenda). A General Electric Company procedire, designed to evaluate fracture toughness recnirements for older plants where

'information may be incomplete, was used to estimate R'I)pp values on an eq11 valent basis to the new recpirements for plants which have construction permits after Augast 15, 1973.

We limiting initial RTgyp value of the RPV core beltline region is 10CF, based on Charpy V-Notch data for plate material. %e

' closure flange region RTgyp is limited by the upper vessel shell plate with a value of 160F based on Charpy data. S e non-beltline discontimity limits for hydrotest (Olrve A in GE 'Ibpical Report NEDC-30997) are based on the R'I}gp for the steam cutlet nozzle of 400F , based or. the dropweight tent temperature. 'Ibe non-beltline discontimity limits for heatup/cooldown (Garve B in GE 'Ibpical Report NEDC-30997) and core critical operation (01rve C in GE Topical Report NEDC-30997) are based on the 400F RTgyp of the steam out-let nozzle, determine (. by Garpy data.

Ficpre 3.6-1 establishes mininum temperature reg 11rements for leak _

testing and hydrostatic testing recnited by the ASME Boiler and Presaire Vessel Code,Section XI.

HA'IUI - UNIT 1 3.6-15

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BASES PTR LIMITING (DEITIONS FOR OPERATION AND SURVEILLANCE REQJIREMENTS 4

Test pressares for inservice hydrostatic and leak testing recuired

. by the ASME B&PV Code,Section XI, are a function of testing tem-perature and component material. For the Hatch 1 reactor presaire vessel, the ISI hydrostatic test presaire would be approximately 1.1 L times-operating presance, or about 1106 psig, depending on the reactor water tenperature. %e temperatures for presaires above 440 psig are determined by the RPV core beltline with a shift in RTgyp of 1230F, appropriate for operation up to 16 effective filll power

years (EPPY) .

i i Fig 2re 3.6-2 provides appropriate limitations for plant heatup and cooldown when the reactor is not critical. Ficpre 3.6-2 is also applicable to low power physics tests. %ese curves asalme heatup i

and cooldown rates up to 1000F per hour. Tenperatures for presaires above 300 psig represent the limits of the RPV core beltline with a shift

in R'I) gyp of 1230F, appropriate for 16 EFPY of operation.

! Fig 2re 3.6-3 establishes operating limits when the core is critical.

I Figure 3.6-3 is not applicable to lc,< power physics tests. %ese limits include a margin of 400F as recuired by 10CFR50 Appendix

G. In accordance with the May 1983 revision of 10CFR50 Appendix G, core critical operation may be initiated at temperatures at or above l (R'I) gyp + 600 F ) of the cloaire flange reg 3on, or 760F. Tempera-

, tures-for presaires above 300 psig represent the limits of the RPV core beltline with a RTgyp shift of 1230F, appropriate for 16 EFPY of operation.

i

%e fracture toughness of all ferritic steels grac11 ally and uni-formly decreases with expoaire to fast naltrons above a threshold value, and it is prudent and conservative to acomant for this in the operation of the RPV. Two types of information are needed in this analysis: (a) a relationship between the change in fracture taugh-ness of the RPV steel and the naltron fluence- (integrated naltron flux); and (b) a meaalre of the naltron fluence at the point of 3 interest in the RPV wall. A method of relating shift in RTgyp to

,. accanulated fast metron (>l MeV) fluence is contained in Regulatory i Glide 1.99, Revision 1. Experimental reallts of irradiated air-l veillance specimens taken from the RPV show a shift in R'I} gyp greater than predicted by Regulatory Glide 1.99, so the alrveillance reallts were used with the methods of 1.99 to establish the RTgyp shift.

%e shift for 16 EPPY was added to the unirradiated RPV core beltline alrves, reallting in the beltline being the limiting region in the vessel for higher presaire-temperature conditions.

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E i3 HA'IG - UNIT 'l 3.6-16

BASES FOR LIMITING CDNDITIONS EDR OPERATION AND SURVEILLANCE REQUIREMENTS 3.6.B. Reactor Vessel 'Demperature and Pressure (Contirued)

%e expected ne2 tron fluence at the reactor vessel wall can be determined at any point chring plant life based on the linear relationship between the reactor thermal power cutput and the corresponding rumber of netrons procliced. Accordingly, neutron flux wires were removed from the reactor vessel with the suveil-lance test specimens to establish the correlation at the capsule location by experimental methods. We flux distrihition at the vessel wall and 1/4 T depth was analytically determined as a function of core height and azinuth to establish the peak flux location in the vessel and the lead factor of the surveillance specimens. Relating the flux wire data to the vessel peak flux analysis location gives a conservative estimate of maxinum 1/4 T depth flux of 1.86 x 109 (n/cm2-sec).

%e first capsule containing test specimens was withdrawn in November 1984 after 5.75 EPPY of operation. We specimens were tested according to AS'IM E185-82 and the results are in GE report NEDC-30997. %e curves of Figures 3.6-1 through 3.6-3 include the findings of the test report related to the copper-phosphorus content of the RPV core beltline materials, the flux wire test and fluence distribution analysis results, and the Charpy V-Notch specimen test results.

C. Reactor Vessel Head Stud Tensioning he recuirements for cold bolt-tip of the reactor vessel closure are ,

based on the R'I) gyp temperature plus 600F which is derived from the recuirements of the ASME Code to which the vessel was tuilt.

%e maxinum R'I} gyp of the closure flanges, adjacent head and shell material and stud material is 160F. The minim 1m temperature for bolt-up is therefore 16 + 60 = 760F. We neutron radiation fluence at the cloaire flanges is well below 1017 nut (>l Mev) and therefore radiation effects will be minor and will not influence this tenperature.

D. Idle Recirculation Icop Startup Recuiring the coolant temperature in an idle recira21ation loop to be within 50'F of the operation loop temperature before a recirculation pamp is started prevents tha potential seiaire of the pump impeller within the wear rings because of the more rapid dimensional increase of the impeller (11 ring heatup arising from thermal capacity.

HA'IG - UNIT 1 3.6-17

('Ihis page intentionally blank) e HNIG UNIT 1

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1600 VAllO TO 16 EFFECTIVE FULL POWER YEARS OF OPERATICA

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1400 1200

.e.

E -

o ADJUSTED CORE BELTLINE,

, at: 1/4 T FLAW, RTNOT

• 100F.

$ 1000 IRRADIATION SHIFT = 1230F CL 5

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g

= ,

10 lE

.d

'N W

• M U

=C W

" VERT; CAL LIMIT LINE FOR PRESSURE M A50% E 274 HYDROTEST 1312 psegl, BASED ON 10CFR$0 APPEN0lX G REQUIREMENT OF IRTNOT + 900F),

FLANGE TIEGION RTNOT = 160F 200 "80LT PMELOAD TEMPERATURE GF

, # 760F 8ASED ON RECOMMENDEO (PTNot

• 600FI FOR 0.24 4N. PLAW IN JLOSURE FLANGE REGION, RTNot a 160F 0

0 100 200 300 400 500 600 MINIMUM VESSEL METAL TEMPERATURE l'F)

Figure 3,6-1 Pressure versus Minimum Temperature for Pressure Tests, Such as Required by ASME Section XI HATCH - UNIT 1

1800 VALID TO 16 EFFECTIVE FULL POWER YEARS OF OPERATION 1400 g 1200 5

5 et

1. 1000 o .

, F-Z

" ADJUSTED CORE SELTLINE t.u 1/4 T FLAW. RTN or = 100F

• . IRRADIATION SHIFT

• 1230p y 8= / l E

d M

y em

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5 cc 400 FEEDWATER NOZ2LE TEMPER ATURE LIMIT FOR 1/4 T FLAW (BWR/6 RESULTS ADJUSTED TO 400F RT NOTI 200 MINIMUM OPERATING TEMPERATURE OF 760F 8ASED ON RECCMMENDEO i

(RTNOT + 600F) FOR 0.24.IN. P LAW IN

[p CLOSURE FLANGE REGION.

RTNOT

• 160F 0

0 100 200 300 400 500 600 MINIMUM VESSEL METAL TEMPERATURE l'FI

. Figure 3,6 2 Pressure versus Minimum Temperature for Non-Nuclear Heatup/Cooldown and Low Power Physics Tests HATCH - UNIT 1

l

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I 1600 VALID TO 16 EFFECTIVE FULL POWER YEARS OF OPERATION 1400 g 1200 m

O m3*

u 1000

$ lI 7- ADJUSTED CORE 8ELTLINE.

1/4 T FLAW RTNOT = 100F.

IRRADIATION SHIFT = 1230F EM 800 0

E d

• Q W 600 5

ti 5

cz:

400 FEEDWATER NOZZLE TEMPERATURE LIMIT FOR 1/4 T FLAW (8WR/6 RESULTS ADJUSTED TO 400F RTNOTI 200 MINIMUM OPER ATING TEMPER ATURE LIMIT OF 760F FROM 10CFR50 APPENDIX G R EQUIREMENT THAT (TMIN = RTNDT + 600F).

FLANGE RTN or = 160F 0 100 200 300 400 500 600 MINIMU'1 VESSEL METAL TEMPERATURE (*F1

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Figure 3,6-3 Pressure versus Minimum Temperature for Core CritiLal Operation other than Low Power Physics Tests (Includes 40*F Margin Required by 10CFR50 Appendix G)

! HATCH UNIT 1

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