ML20024H410

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Revised Proposed Tech Specs Re Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens
ML20024H410
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 05/24/1991
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20024H409 List:
References
NUDOCS 9106030282
Download: ML20024H410 (10)
v • d • e


Text

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NITACllMENT A UNIT 1 REVISED TECilNICAL SPECIFlCNI1ON PAGES

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3/4 4-23 3/4 4-25 B3/4 4 5 l-l l

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9106030282 910524 PDR ADOCK v5000317 P PDR

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REACT 0D COOLANT SYSTEM .

3/4.4.9 PRESSURE /TEMPEDATURE LIMITS I REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figure 3.4 2 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:

a. A maximum heatup of:

Maximum Allowable Heatuo Rate RCS Temoerature 40VF in any one hour period 70UF to 313PF 100 F in any one hour period 3140 F to 327 0F 600 F in any one hour period > 3270F

b. A maximum cooldown of:

Mavimum Allowable Cooldown Rate RCS Temperature 100R F in any one hour period > 2500F 200 F in any one hour period 2500 F to 170 0F 100 F in any one hour period < 1700F

c. A maximum temperature change of 05 F in any one hour period, during hydrostatic testing operations above system design pressure.

APPLICABILITY: At all times.

ACTION:

With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the

, fracture toughness properties of the Reactor Coolant Syrtem; detennine that the Reactor Coolant System remains acceptable for continued operations or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS T and pressure to less than 200 0F and 300 psia, respectively,wildnthefollowing30 hours. -

SURVEILLANCE RE0VIREMENTS e

l 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be ,

detennined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.

4.4.9.1.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined g to determine changes in material l properties, at the intervals whcwn in != ' ' 5B The results of these l examinations shall be used to update Figure _3.4-2f _ _

reguired [/0 CFR Pa AppewAh d.

CALVERT CLIFFS - UNIT 1 3/4 4-23 6edmentNo.J/J,///3

. ,7 TABLE 4.4 EACTOR VESSEL MATERIAL IRRADIATION SURVEILLANCE SCHEDULE SPECIMEN-  !

REMOVAL INTERVAL

1. . Capsule No. 1 5 years I

-2. Capsule No. 2 14 years I

3. Capsule No. 3 23 years i
4. Capsule No. 4 0 years  !

t

5. Capsule No. 5 35 years /
6. Capsule No. 6 40 years b EL E TE b l

l 1,

CALVERT CLIFFS - UNIT 1 3/4 4-25 6e +~~ '- /k3

REACTOR COOLANT SYSTEM BASES steam generator tube rupture accident in conjunction with an assumed steady state primary-to secondary steam generator leakage rate of 1.0 gpm and a concurrent loss of offsite electrical power. The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in that specific site paometers of the Calvert Cliffs site, such as site boundary location and meteorological conditions, were not considered in this evaluation. The NRC is finalizing site specific criteria which will be used as the basis for the reevaluation of the specific activity limits of this site. This reevaluatior, may result in higher limits.

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity >1.0 uti/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER. Operation with specific activity levels exceeding 1.0 uCi/ gram ?OSE EQUIVALENT I-131 but within the limits shown on Figure 3.4-1 must be restricted to no more than 10 percent of the unit's yearly operating time since the activity levels allord by Figure 3.4-1 increase the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thyroid dose at the site bouncary by a factor of up to 20 following a postulated steam generator tube rupture.

Reducing T a to < 500 F prevents the release of activity should a steam generator dbe rupture since the saturation pressurc of the primary coolant is below the lift pressure of the atmospheric steam relief valves. The surveillance requireaents provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained, b.

n 3/4,4.9 PRESSURE / TEMPERATURE LIMITS I$#

H Operation within the appropriate heatup and cooldown curves assures the integrity of the reactor vessel against fracture induced by combinative thermal and pressure stresses. As the vessel is subjected to -

increasing fluence, the toughness of the limiting material continues to decline, and ever more restrictive Pressure / Temperature limits must be observed. The current limits, Figures 3.4-2a and 3.4-2b, are for up to a, and including 12 Effective Full Power Years (EFPY) of operation.

Q

$ ~% , _ RTNDT, _ . Theisshift in the material fracture toughness, as represented by calculated using Regulatory Guide 1.99, Revision 2. For 12 EFFT, at the 1/4 T position, the adjusted reference temperature (ART)

CALVERT CLIFFS - UNIT 1 B 3/4 4-5 Amendment No. [h

INSERTS FOR BASES SECTION 3/4.4.9

' PRESSURE / TEMPERATURE LIMFIS' INSERT"A" All components in the Rer.ctor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes. These cyclic lords are introduced by normal load transients, reactor trips, and startup and shutdown operation. The various categories of load cycles used for design piirposes are prosided in Section 4.1.1 of the UFSAR. During startup and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.

INSE9T #B" The reactor vessel materials have been tested to determine their initial RTNDT; the results of these tests are shown in Section 4.1.5 of the UFSAR. Reactor operation and resultcut fast neutron (Ed1 Mev) irradiation will cause an increase in the RTNDT. The actual shift in RTNDTOf the vessel material will be established periodically during operation by removing and evaluating reactor vessel materialirradiation surveillance specimens installed near the inside wall of the reactor vessel in the ecre area. The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in UFSAR Table 4-13 and are approved by the NRC prior to implementation in compliance with the requirements of Appendix H to 'i0 CFR Part 50.

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i NITACllMENT H  ;

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UNIT 2 REVISED I TECilNICAL SPECIFICATION  ;

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!- PAGES i a

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i B3/4 4 5  ;

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i REACTOR COOLANT SYSTEM -

SURVEILLANCE REQUIREMENTS i-

4. 4. 9.1.1 The Reactor Coolant System temperature and pressure shall be detennined to be within the limits at least once per 30 minutes during system heetup, cooldown, and inservice leak and hydrostatic testing operations.

4.4.9.1.2 The reactor vessel material irradiation surveillance speci.

mens shall be removed and examined, to determine changes in material properties, at the intervals,lrhei.n 6 Te n ;.; M The results of these examinations shall be used to update Figure 3.4 2.

re 're oCFRP,t50l Apres 1 A.

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4 CALVERT CLIFFS-UNIT 2 3/4 4-2.4 Amhg No.

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IABLE 4.4 5 EACTOR VESSEL MATERIAL IRRADIATION SVRVEILLANCE SCHEDULE SPECIME REMOVAL INTERVAL

1. Capsule No. 1 5 years

{ '

2. Capsule No. 2 14 years
3. Capsule No. 3 23 years .
4. Capsule No. 4 0 years l
5. Capsule Fo. 5 35 y s Capsule No. 6 40 years h EL E TE.h e

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CALVERTClif[$-UNIT 2 3/4 4 26 ' A ud ed th, l

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, REACTOR COOLANT SYSTEM W ES cteam generator tube rupture accident in conjunction with an assumed steady state primkry to. secondary steam generator leakage rate of 1.0 gpm and a concurrent loss of offsite electrical power. The values for the limits on specific activity represent interin limits based upon a parametric evaluation b,v the NRC of typical site locations. These val ws are conservative in that 4pecific site parameters of the Calvert Cliffs site, such as site boundary location and meteorological conditions,cuore not considered in this evaluation. The NRC is finalizing site specific criteria which will be used as the basis for the reevaluation of the specific activity limits of this site. ' This reevaluation may result.tn higher limits.

The ACTION siatement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity

>l.0 uti/ gram DOSE EQUIVALEU I-131 but within the allowable limit shown on Figure 3.41, accomodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER. Operation with specific activity levels exceeding 1.0 uti/ gram DOSE EQUIVALENT !.131 but within the limits shown on Figure 3.4 1 must be restricted to no more than 10 percent of the unit's yearly operating time since the activity levels allowed by Figure 3.4 1 increase the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thyroid dose at the site boundary by a factor of up to 20 following a postulated steam generator tube rupture.

Reducing T to < 5000 F prevents the release of activity should a steam generator,Nbe rupture since the saturation pressure of the primary coolant is below the lift pressure of the attuospheric steam relief valves. The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected.fn sufficient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters p associated with spiking phenomena. A reduction in frequency of isotopic q analyses following power changes may be permissible if justified by the ,

g data obtained.

'"S 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Operation within the appropriate heatup and cooldown curves assures the integrity of the reactor vessel against fracture induced by combinative thermal and pressure stresses. As the vessel is subjected to increasing fluence, the toughness of the limiting material continues to -

decline, and even more restrictive Pressure / Temperature limits must be observed. The current limits. Figures 3.4 2b and 3.4 2c, are for up to i b -

and including 12 Effective full Power Years (EFPY) of operation.

I M lo g The shift in the material fracture toughness,- as represented by -(

r M RT is calculated using Regulatory Guide 1.99, Revision 2. For 12 '

EFNT,tthe1/4Tposition,theadjustedreferencetemperature(ART)

,a

]  ;

O

l INSERTS FO'R BASES SECTION 3/4.4.9

)

' PRESSURE / TEMPERATURE LIMIT 3' INSERT *A'

. All components in the Reactor Coolant System are designed to withstand the effects of cylic ,

loads due to system temperature and pressure changes. nese cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdswa operation. De various categodes of load cycles used for design purpose a:e provided in Section 4.1.1 of the UFSAR. During startup and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.

9 INSERT *B*

Re reactor vessel materials have been tested to determiae their initial RTNDT; the results of these tests are shown in Section 4.1.5 of the UFSAR. Reactor operation and resultant fast 1

neutron (E>1 Mev) irradiation will cause an increase in the RTNDT. The actual shift in RTNDTOf the vessel material will be established periodically during operation by removing and evaluating ,

i reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor l vessel in the core area. We number of reactor vessel irradiation surveillance specimens and the frequencies for removing and esting these specimens are provided in UFSAR Table 4-13 and are epprUved by the NRC prie .o implementation in compliance with the requirements of Appendix H $

to 10 CFR Part 50.

1 E

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