Text

Informs NRC of Changes Util Made to Plant,Units 1,2 & 3 TS Bases & Fuel Bundle Weight Was Revised to Reflect Lighter Weight of GE11 Fuel Design
	ML20094M759
Person / Time
Site:	Browns Ferry
Issue date:	11/17/1995
From:	Salas P; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20094M762	List: ML20094M759; ML20094M770;
References
	TVA-BFN-TS-370, NUDOCS 9511270214
	Download: ML20094M759 (32)
	v • d • e

,

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

LYA Tennessee Valley Authority. Post Office Box 2000, Decatur, Alabama 35609 November 17, 1995 TVA-BFN-TS-370 10 CFR 50.90 U.S. Nuclear Ret <

ory Commission ATTN:

Document c.>. rol Desk Washington, D.C.

20555 Gentlemen:

In the Matter of

)

Docket Nos. 50-259 Tennessee Valley Authority

)

50-260 50-296 l

BROWNS FERRY NUCLEAR PLANT f,LFN) - UNITS 1, 2, AND 3 -

REVISION TO TECENICAL SPECIFICATION (TS) BASES (TS-370)

The purpose of this letter is to inform NRC of changes TVA made to the BFN Units 1, 2,

and 3 TS Bates.

These changes provide consistency between the Units 2 and 3 TS Bases.

The fuel bundle weight was revised to reflect the lighter weight of the Gell fuel design. provides a description of the Bases changes. contains marked up copies of the appropriate Units 1, 2,

and 3 Bases to show the changes.

forwards the revised Units 1, 2,

and 3 Bases pages for TS-370.

b 9511270214 951117 09 PDR ADOCK 05000259

\\

P PDR 5

U.S. Nuclear Regulatory Commission Page 2

. November 17, 1995 There are no commitments contained in this letter.

If you have any questions about these changes, please contact me at (205)729-2636.

rdly s

' alas Manager of Site Licensing i

Enclosures cc (Enclosures):

Mr. W. D. Arndt General Electric Company 735 Broad Street j

Suite 804, James Building Chattanooga, Tennessee 37402 Mr. Johnny Black, Chairman Limestone County Commission 310 West Washington Street Athens, Alabama 35611 Mr. Mark S.

Lesser, Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. Joseph F. Williams, Project Manager U.S. Nuclear Regula tory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Dr. Donald E. Williamson State Health Officer Alabama State Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-3017

I i

}

ENCLOSURE 1 i

i TENNESSEE VALLEY AUTHORITY BROWNS PERRY NUCLEAR PLANT (BPN) i UNITS 1, 2, AND 3 PROPOSED TECENICAL SPECIPICATION (TS) CEANGE TS-370 DESCRIPTION AND EVALUATION OP THE PROPOSED CHANGE i

f Is DESCRIPTION OP THE PROPOSED CRANGE TVA revised Units 1, 2,

and 3 TS Bases to revise the fuel bundle weight to reflect the lighter weight of the Gell i

fuel design and to provide consistency between Units 2 and 3 TS Bases.

The changes are detailed in the attached Table that provides a comparison of the Units 2 and 3 TS Bases.

II.

REASON POR THE PROPOSED CEANGE These changes were the result of a comparison of the Units 2 and 3 TS Bases.

They are administrative in nature and provide for consistency between the TS Bases for Unite 2 and 3.

The fuel bundle weight for Units 1, 2, and 3 ss revised to reflect the lighter weight of the Gell fuel design.

l 3

t i

Technical Specification Change 370 s

List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision l

(Section/Page/ Text)

(Affected Unit / Text) 1

1.1 Bases

Fuel Claddina Intearity Safety Limit

1.1 Bases

Fuel Claddna Inteority Safetv Umit Revise Urut 3 to match Unit 2.

l Page 1.1/2.1-8, second paragraph, last sentence -

Page 1.1/2.1-8, second paragraph, last sentence -

f MCPR > 1.07 represents a conservahve margin relative This MCPR represents a conservative margin relative i

to the condtions required to maintain fuel cladding to the conditions required to maintain fuel cladding integnty.

integnty.

2

1.1 Bases

Fuel Claddng Integnty Safety Umit

1.1 Bases

Fuel Cladding integrity Safety Umit Revise Unit 2 to match Unit 3.

j Page 1.1/2.1-8, third paragraph, third sentence -

Page 1.1/2.1-8, third paragraph, third sentence -

The margin for each fuel assembly is characterized by The margin for each fuel assembly is characterized by l

the entical power ratio (CPR) which is the ratio of the the critical power ratio (CPR) which is the ratio of the bundle power which would produce onset of transition bunde power which would produce onset of transiton I

boiling, dvided by the actual bunde power.

boiling dvided by the actual bunde power.

3

1.1 Bases

Fuel Claddng Integrity Safety Umit

1.1 Bases

Fuel Claddng integrity Safety Umit Rt. wise Unit 3 to match Unit 2.

Page 1.1/2.1-8, third paragraph, sixth sentence -

The Safety Umst (MCPR of 1.07) has sufficient The Safety Umit (MCPR of 1.07) has sufficient conservatism to assure that in the event of an abnormal conservatism to assure that in the event of an abnormal operational transient initiated from a normal operating operational transient initiated from a normal operabng conditon (MCPR > limits specified in Specification condtion (MCPR > *) more than 99.9 percent of the 3.5.K) more than 99.9 percent of the fuel rods in the fuel rods in the core are expected to avoid boiling core are expected to avoid boiling transition.

transiton.

i i

Bottom of page 1.1/2.1-8 "See Section 3.5.K i (11/14/95-0655) f s

Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Section/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) 4

1.1 Bases

Fuel Cladding Integrity Safety Umit

1.1 Bases

Fuel Cladding integnty Safety Umit Revise Unit 3 to match Unit 2.

Page 1.1/2.1-9, second paragraph, second sentence -

Cladding temperatures would increase to approximately Claddmg temperatures would increase to approximately 1,100*F which is below the perforation temperature of 1100*F which is below the perforation temperature of the claddng material.

the cladding material.

5

1.1 Bases

Fuel Cladding Integnty Safety Umit

1.1 Bases

Fuel Cladding Integrity Safety Umit Revise Unit 3 to match Unit 2.

Page 1.1/2.1-9. third paragraph, first sentence -

Page 1.1/2.1-9, third paragraph, first sentence -

If reactor pressure should ever exceed 1,400 psia If reactor pressure should ever exceed 1400 psia dunng during normal power operation.

normal power operation.

6

1.1 Bases

Fuel Cladding integrity Safety Umit

1.1 Bases

Fuel Cladding Integrity Safety Umit Use the following wordmg from NUREG 1433, Revision 1, Section B 2.1.1, for Unit 2 and Unit 3:

Page 1.1/2.1-9, fourth paragraph, third sentence -

Since the pressure drop in the bypass region is Since the pressure drop in the bypass region is Since the pressure drop in the bypass region is essentiany an elevation head, the core pressure drop at essentially all elevation head, the core pressure drop at essentially all elevation head, the core pressure drop at low power and flows will always be greater than 4.5 low powers and flow wiB always be greater than 4.56 low powers and flows will always be greater than 4.56 psi.

psi.

psi. (WW9s - 06:55)

i

+

i i

Technical Specification Change 370 I

l List of Bases Changes for. Units 2 and 3 i

Unit 2 Unit 3 Revision i

(Section/Page/ Text)

(Sec6on/Page/ Text)

(Affected Unit / Text) i t

7 2.1 Bases 2.1 Bases Revise Unit 3 to match Unit 2.

{

Page 1.1/2,1-13, first paragraph, first sentence -

Page 1.1/2.1-13, first paragraph, Hrst sentence -

l Analyses of the hmiting transients show that no scram Analyses of the limiting transients show that no scram adjustment is required to assure MCPR > 1.07 when adjustment is required to assure MCPR > 1.07 when I

the transient is initiated from MCPR limits specified in the transient is initated from MCPR >*".

I Specification 3.5.k.

I Bot'om of page 1.1/2.1-13 "*See Section 3.5.K 8

2.1 Bases 2.1 Bases Revise Unit 2 to match Unit 3.

Page 1.1/2.1-13, second paragraph. -

Page 1.1/2.1 13, second paragraph, -

[

. constrained to be uniform by operating

[

procedures backed up by the rod worth minimizer procedures becked up by the rod worth minimizer.

l Thus, of all possible sources of reacivity input, uniform Worth of Individual rods Is very low in a uniform f

l control rod.

rod pattern. Thus, of all possible sources of reactivity l

ir,,xJt, uniform control rod.

i 9

2.1 Bases 2.1 Bases Revise Unit 3 to match Unit 2.

I t

i Page 1.1/2.1-13, third paragraph, first, second, and Page 1.1/2.1-13, third paragraph, first, second. and

}

third sentence -

l The IRM System consists of eight chambers, four in The IRM System consists of 8 chambers,4 in each of

}

each of the reactor protection system logic channels.

the reactor protection system logic channels. The IRM The IRM is a five-decade instrument which covers the is a 5-decade instrument which covers the range of range of power level between that covered by the SRM power level between that covered by the SRM and the

{

and the APRM. The five decades are covered by the APRM. The 5 decades are covered by the IRM by IRM by means of a range switch and the five decades means of a range switch and the 5 decades are broken

~

are broken down into..

down into....

6 (11n4/95 - OsSs) i

- m

m..

. m..

m m

.m m

m.

Technical Specification Change 370 List of Bases Changes for Units 2 and 3 t

i Unit 2

' Unit 3 Revision I

(Secton/Page/ Text)

(Sechon/Page/ Text)

(Affected Unit / Text) j 10 2.1 Bases 2.1 Bases Revise Unit 2 and Unit 3 as follows:

Page 1.1/2.1-13, third paragraph, last sentence -

For example, if the instrument was on range 1, the scram setling would be 120 divisions for that range; For example, if the instrument were on range 1, the For example, if the instrument was on range 1, the likewise if the instrument was on range 5, the scram I

scram setting would be at 120 divisions for that range; scram sethng would be 120 divisions for that range; setting would be 120 divisions for that range.

hkewise if the instrument was on range 5, the scram likewise if the instrument was on range 5, the scram i

set 6ng would be 120 divisions on that range.

setting would be 120 divisions on that range.

I 11 2.1 Bases 2.1 Bases Revise Urut 3 to match Unit 2.

f I

Page 1.1/2.1-14, first paragraph, third sentence -

i in addition, the APRM 15 percent scram prevents The APRM 15 percent scram will prevent higher power l

higher power operation without being in the RUN mode.

operation without being in the RUN mode.

a 6

12 2.1 Bases 2.1 Bases Revise Unit 3 to match Unit 2.

j Page 1.1/2.1-14, first paragraph, sixth sentence -

Page 1.1/2.1-14, first paragraph, sixth sentence -

For insequence control rod withdrawal, the rate of For insequence control rod withdrawal, the rate of 1

change of power is slow enough due to the physical change of power is slow enough, due to the physical i

limitation of withdrawing control rods that heat flux is in limitation of withdrawing control rods, that heat Aux is in equilibrium with the neutron flux.

equihbrium with the neutron flux.

l i

i i

13 2.1 Bases 2.1 Bases Revise Unit 2 to match Unit 3.

Page 1.1/2.1-14, first paragraph, seventh sentence -

Page 1.1/2,1-14, first paragraph, seventh sentence -

l i

An IRM scram would result in a reactor shutdown well An IRM scram would result in a reactor shutdown well before any safety Ilmit is exceeded.

before any SAFETY LIMIT is exceeded t

l (11/14/95 - OS 55) m-..

m..

m.

m

.m m

m m

m.

.m-mm m m

..- - m

t Technical Specification Change 370 List of Bases Changes for Units 2 and 3 I

Unit 2 Unit 3 Revision (Section/Page/ Text)

(SectionFage/ Text)

(Affected Unit / Text) 14 2.1 Bases 2.1 Bases Revise Unit 2 and Unit 3 as fonows:

Page 1.1/2.1-14, first paragraph, twelfth sentence -

Page 1.1/2.1-14 first paragraph, twelfth sentence -

Quarter rod density is discussed in paragraph 7.5.5.4 of the FSAR.

Quarter rod density is illustrated in paragraph 7.5.5 of Quarter rod density is illustrated in paragraph 7.5.5.4 of the FSAR.

the FSAR.

15 2.1 Bases 2.1 Bases Revise Unit 2 to match Unit 3.

Page 1.1/2.1-14, second paragraph, last sentence -

Licensing analyses have demonstrated that with a Licensing analyses have demonstrated that with a neutron.. violate the fuel safety limit and there is a neutron.. violate the fuel SAFETY LIMIT and there is 6

substantial margin from fuel damage.

a substantial margin from fuel damage.

16 2.1 Bases 2.1 Bases Revise Unit 2 to match Und 3.

l

[

Page 1.1/2.1-15 Title for item C. -

Reactor Water Low Level Scram and Isolation (Except Reactor Water Low Level Scram and Isolation (Except Main Steam lines)

Main Steam Lines) 17 2.1 Bases 2.1 Bases Revise Unit 3 to match Unit 2.

Page 1.1/2.1-16, first paragraph, first sentence -

The low pressure isolation of the main steam lines at The low pressure isolation of the main steam ines at 825 psig was provided to protect against rapid reactor 850 psig was provided to protect against rapid reactor depressurization and the resulting rapid cooldown of the depressurization and the resulting rapid cooldown of the vessel.

vessel.

-s-(iinas - oess)

=

Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Section/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) 18 2.1 Bases 2.1 Bases Revise Unit 2 to match Unit 3.

Page 1.1/2.1-16, first paragraph, second sentence -

Page 1.1/2.1-16, Arst paragraph, second sentence -

The scram feature that occurs when the main steamline The scram feature that occurs when the main steam

. fuel cladding integrity safety limit.

line.. fuel cladding integrity SAFETY LIMIT.

i f

19 2.1 Bases 2.1 Bases Revise Unit 2 and Unit 3 as follows:

Page 1.1/2.1-16, first paragraph, third sentence -

Page 1.1/2.1-16 first paragraph, third sentence -

Operation of the reactor at pressures lower than 825 psig requires that the reactor mode switch be in the Operation of the reactor at pressures lower than 525 Operation of the reactor at pressures lower than 850 STARTUP position, where protection of the fuel psig requires that the reactor mode switch be in the psig requires that the reactor mode switch be in the dadding integrity SAFETY LIMIT is provided by the STARTUP position, where protection of the fuel startup position, where protection of the fuel dadding IRM and APRM high neutron flux scrams.

cladding integrity safety limit is provided by the IRM integrity SAFETY LIMIT is provided by the IRM and and APRM high neutron flux scrams.

APRM high neutron flux scrams.

f i

20 2.1 Bases 2.1 Bases Revise Unit 2 to match 3.

Page 1.1/2.1-16, first paragraph, fourth sentence -

Thus, the combination of rnain steamline.. fuel Thus, the combination of main steam line.. fuel cladding integnty safety limit.

dadding integrity SAFETY LIMIT.

s (11/14/95 - 06.55) l t

u-

Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Section/Page/ Text)

(Section/PagesText)

(Affected Unit / Text) 21 1.2 Bases 1.2 Bases Revise Unit 2 and Unit 3 as follows:

Page 1.2/2.2-2, third paragraph, first sentence -

Correspondingly, the design pressures (1,148 for suction and 1,326 for discharge) of the reactor Correspondingly, the design pressure (1,148 psig for Correspondingly, the design pressure (1,148 psig for recirculation system piping are such that, when the 20 suction and 1,326 psig for discharge) of the reactor suction and 1,326 psig for discharge) of the reactor percent allowance (230 and 265 psi) aHowed by USAS recirculation system piping Is such that, when the 20 recirculation system piping are such that, when the 20 Piping Code, Section B31.1 for pressure transients is percent allowance (230 and 265 psi) allowed by USAS percent anowance (230 and 265 psi) aHowed by USAS added to the design pressures, transient pressure limits Piping Code, Section B31.1 for pressure transients is Piping Code, Section B31.1 for pressure transients are of 1,378 and 1,591 psig are established.

added to the design pressures, transient pressure limits added to the design pressures, transient pressure limits of 1,378 and 1,591 psig are estatdished.

of 1,378 and 1.591 psig are established.

22 1.2 Bases 1.2 Bases Revise Reference 1 of the Sechon 1.2 Bases for both Unit 2 and Unit 3 as fonows:

Page 1.2/2.2-3, References -

Pege 1.2/2.2-3, References -

1. Plant Safety Analysis (BFNP FSAR Septions 14.0

1. Plant Safety Analysis (BFNP FSAR Section 14.0).

1. Plant Safety Analysis (BFNP FSAR Section N 14.0).

and Appendix N).

I 23 1.2 Bases 1.2 Bases Revise Unit 2 to match Unit 3.

Page 1.2/2.2-3, References -

s Unit 2 only has 4 references.

5. Generic Reload Fuel Application, Licensing i

Topical Report, NEDE-24011-P-A and Addenda.

?

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! (11/14.9s - os.55) b u

Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Section/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) 24 2.2 Bases 2.2 Bases Revise Unit 3 to match Unit 2.

Page 1.2/2.2-4, first paragraph, first sentence -

To meet the safety basis,13 relief valves have been To meet the safety basis 13 relief valves have been installed on the unit with a total capacity of 84.1 percent installed on the unit with a total capacity of 83.77 of nuclear boiler rated steam flow.

percent of nuclear boiler rated steam flow.

25 2.2 Bases 2.2 Bases Revise Unit 3 to match Unit 2.

Page 1.2/2.2-4, first paragraph, second sentence -

The analysis of the worst overpressure transient (3-The analysis of the worst overpressure transient, (3-second closure of a!! main.

second closure of all main.

26 3.1 Bases 3.1 Bases Revise Unit 2 to match Unit 3.

Page 3.1/4.1-14, first caragraph, first sentence -

Page 3.1/4.1-13, first paragraph, first sentence -

The reactor protecton system automatically initiates a The Reactor Protection System automatically initrates a reactor scram to:

reactor scram to:

27 3.1 Bases 3.1 Bases Revise Unst 2 to match Unit 3.

Page 3.1/4.1-14, second paragraph, first sentence -

Page 3.1/4.1-13, second paragraph, first sentence -

This specification provides the Ilmiting conditions for This specification provides the LIMITING CONDITIONS operation necessary to preserve the ability of the FOR OPERATION necessary to preserve the ability of system.

the system. (11114/95 - o6:55)

1 e

Technical Specification Change 370 l

List of Bases Changes for Units 2 and 3 u

Unit 2 Unit 3 Revision i

(Section/Page/ Text)

(Sechon/Page/ Text)

(Affected Unit / Text)

}

28 3.1 Bases 3.1 Bases Revise Unit 2 to match Unit 3.

l I

Page 3.1/4.1-14, second paragraph, last sentence -

Page 3.1/4.1-13, second paragraph, last sentence -

When necessary, one channel may be made When necessary, one channel may be made INOPERABLE for briefintervals to conduct required inoperable for brief intervals to conduct required functional tests and cahbrations.

functional tests and calibrations.

l t

29 3.1 Bases 3.1 Bases Revise Unit 2 to match Unit 3.

I Page 3.1/4.1-14, fourth paragraph, first sentence -

Page 31/4.1-13, fourth paragraph, first sentence -

9 i

The reactor protection system is made up of two The Reactor Protection System is made up of two i

independent trip systems (refer to Section 7.2. FSAR).

independent trip systems (refer to Section 7.2, FSAR).

j l

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30 3.1 Bases 3.1 Bases Revise Unit 2 to match Unit 3.

L Page 3.1/4.1-15, first paragraph, last sentence -

Page 3.1/4.1-14, first paragraph, last sentence -

The bases for the scram setbng for the IRM, APRM, The bases for the scram setting for the IRM, APRM,.

high reactor pressure, reactor low water level, MSIV high reactor pressure, reactor low water level, MSIV dosure, turbine control valve fast dosure and turbine dosure, turbine control valve fast dosure, and turbine

[

stop valve dosure are discussed in Specifications 2.1 stop valve dosure are discussed in Specifications 2.1 and 2.2.

and 2.2.

I b

-e.

(11/14/95 - 06 S5)

L h

i

[

?

Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit ?

Unit 3 Revision (Section/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) 31 3.1 Bases 3.1 Bases Revise Unit 3 to match Unit 2.

Page 3.1/4.1-16, fifth paragraph, third sentence -

Page 3.1/4.1-15, fifth paragraph, third sentence -

For normal operating conditions, these limits.. full For normal operating conditions, these limits.. full power and from full power to SHUTDOWN).

power and from full power to shutdown).

32 4.1 Bases 4.1 Bases Revise Unit 2 to match Unit 3.

Page 3.1/4.1-17, third paragraph, second sentence -

Page 3.1/4.1-16, third paragraph, second sentence -

During design, a goal of 0.9999 probability of success During design, a goal of 0.99999 probability of success (at the 50 percent confidence level) was adopted to (at the 50 percent confidence level) was adopted to assure that a balanced and adequate design is assure that a balanced and adequate design is achieved.

achieved.

I 33 4.1 Bases 4.1 Bases Revise Unit 3 to match Unit 2.

Page 3.1/4.1-17, item C. -

Page 3.1/4.1-16, item C. -

Devices which only serve a useful function during some Devices which only serve a useful function during some restricted mode of.. that can be performed at restricted mode of.. that can be performed at SHUTDOWN.

shutdown.

- to -

(11/1495-o631)

Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Section/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) 34 4.1 Bases 4.1 Bases Revise Unit 2 and Unit 3 as follows:

Page 3.1/4.1-19, fourth paragraph, second sentence -

Page 3.1/4.1-18, fourth paragraph, second sentence -

For those devices which employ ampl;fiers, etc., dnft specifications call for drift to be less than 0 4 For those devices which employ amplifiers, etc., dnft For those devices which employ amphfiers, etc., dnft percent / month; i e., in the period of a month a drift of specifications call for drift to be less than 0.4 specifications call for drift to be less than 0 4 0.4-percent would occur thus providing for adequate percent / month; i.e., in the period of a month a drift of 4 percent / month; i.e., in the period of a month a drift of margin.

percent would occur and thus providing for adequate

.4-percent would occur and thus providing for adequate margin.

margin.

35 3.2 Bases 3.2 Bases Revise Unit 2 to match Unit 3.

Page 3 2/4.2-65, third paragraph, last sentence -

Page 3.2/4.2-64, third paragraph, last sentence -

Such instrumentation must be available whenever Such instrumentation must be available whenever primary containment integrity is required.

PRIMARY CONTAINMENT INTEGRITY is required.

I 36 3.2 Bases 3.2 Bases Revise Unit 3 to match Unit 2.

Page 3 214.2-65, fifth paragraph -

Page 3.2/4 2-64, fifth paragraph, last sentence -

Unit 3 has a sentence at the end of the paragraph that The RCIC and ifPCI system initiation opens the unit 2 does not have.

turbine steam supply valve which in turn initiates closure of the respective drain valves (Group 7). (11/14.95-o631)

Technical Specification Change 370 r

List of Bases Changes for Units 2 and 3 i

Unit 2 Unit 3 Revision (Section/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) i 37 3.2 Bases 3.2 Bases Revise Unit 3 to match Unit 2.

Page 3.2/4.245, sixth paragraph, first sentence -

Page 3.2/4.244, sixth paragraph, first sentence -

The low water level instrumentation set to trip at 2 398 The low water level instrumentation set to trip at 2 398 I

inches above vessel zero (Table 3.2.A) closes the Main inches above vessel zero (Table 3.2.B) closes the Main 1

Steam isolation Valves, the Main Steam Line Drain Steam Isolation Valves, the Main Steam Line Drain Valves, and the Reactor Water Sample Valves (Group Valves, and the Reactor Water Sample Valves (Group 1).

1).

i

?

t 38 3.2 Bases 3.2 Bases Revise Unit 2 to match Urut 3.

f Page 3.2/4.247, fourth paragraph, third sentence -

Page 3.2/4.246, fifth paragraph, third sentence -

6 i

Each trip system consists of two elements.

Each trip system consists of two channels.

i j

i 39 3.2 Bases 3.2 Bases Revise Unit 3 to match Unit 2.

j i

Page 3.2/4.248, third paragraph -

Page 3.2/4.247, third paragraph -

[

s When the RBM is required, the minimum Instrument The minimum instrument channel requirements

'i channel requirements apply. These requirements assure sufficient instrumentation to assure the assure sufficient instrumentation to assure the single failure criteria is met. The minimum i

single failure celteria is met. The minimum instrument channel requirements for the RBM may l

Instrument channel requirements for the RBM may be reduced by one for maintenance, testing, or be reduced by one for maintenance, testing, or calibration. This does not significantly increase the calibration. This does not significantly increase the risk of an inadvertent control rod withdrawal, as the f

risk of an inadvertent control rod withdrawal, as the other channel is available, and the RBM is a backup t

other channelis available, and the RBM is a backup system to the written sequence for withdrawal of i

system to the written sequence for withdrawal of control rods.

~

i control rods.

I I (1v14/95 - osa1)

'I I

t t

i

Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Section/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) 40 4.2 Bases 4.2 Bases Revise Unit 3 to match Unit 2.

Page 3.2/4.2-72, ttle -

Page 3.2/4.2-70, title -

4.2 BASES (Cont'd)

Unit 3 does not have a ttle for this page.

41 4.2 Bases 4.2 Bases Revise Unit 3 to match Unit 2.

Page 3.2/4.2-72, second paragraph -i = V 2(0 5)

Page 3 2/4.2-70, second paragraph -i = V 2(0.5) 10

10

I 42 4.2 Bases 4.2 Bases Revise Unit 3 to match Unit 2.

I Page 3.2/4.2-72, third paragraph, last sentence -

Page 3.2/4.2-70, third paragraph -

The checks which are made on a daily basis are The checks which are made on a daity basis are adequate to assure OPERABILITY of the sensors and adequate to assure operability of tha sensors and electronic.

electronic.

43 3 3/4.3 Bases 3.3/4.3 Bases Revise Unit 3 to match Unit 2.

Page 3 3/4.3-14, first paragraph, first sentence -

Page 3.3/4.3-14, first paragraph, first sentence -

2.

Reactiviu Marcin -Inoperable Control Rods -

2.

Reactivity maroin -inoperable control rods -

Specification 3.3 A.2.

Specification 3.3A2. (t tt14ss - os21)

9 Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Section/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) 44 3 3/4.3 Bases 3.3/4.3 Bases Revise Unit 2 to match Unit ::

Page 3 3/4.3-15, first paragraph, first sentence -

Page 3.3/4.3-15, first paragraph, first sentence -

2.

The control rod housing support restricts the

2. The control rod housing support restricts the outward movement of a control rod to less than 3 outward movement of a control rod to less than inches in the extremely remote event of a housing three inches in the extremely remote event of a failure.

housing failure.

45 3.3/4.3 Bases 3.3/4.3 Bases Revise Unit 2 and Unit 3 as follows:

Page 3.3/4.3-17, second paragraph -

Page 3.3/4 3-17, second paragraph -

The control rod system is designed to bring the reactor subcntical at a rate fast enough to prevent fuel The control rod system is designated to bring the The control rod system is designated to bring the damage; i e., to prevent the MCPR from becoming less reactor subcritical at the rate fast enough to prevent reactor subcritical at a rate fast enough to prevent fuel than 1.07. The limiting power transients are given in fuel damage; i e., to prevent the MCPR from becoming damage; i e., to prevent the MCPR from becoming less Reference 1. Analysis of these transients phows that less than 1.07. The Ilmiting power transient is given than 1.07. Analysis of this transient shows that the the negative reactivity rates resutting from tne scram in Reference 1. Analysis of this transient shows that negative reactivity rates resultmg from the scram with the average response of all drives as given in the the negative reactivity rates resulting from the scram (FSAR Figure N3.6-9) with the average response of all above specification provide the required protection and with the average response of all the drives as given in the drives as given in the above specification, provide MCPR remains greater than 1.07 the above specification provide the required protection, the required protection, and MCPR remains greater and MCPR remains greater than 1.07.

than 1.07.

46 3.3/4.3 Bases 3.3/4.3 Bases Revise Unit 3 to match Unit 2.

Page 3.3/4.3-17, third paragraph, first sentence -

Page 3.3/4 3-17, third paragraph, first sentence -

On an early BWR, some degradation of control rod On an earfy BWR, some degradation of control rod scram performance occurred during plant STARTUP scram performance occurred during plant startup and and was determined.

was determined. (11/14/95 - 06.31)

Technical Specification Change 370 f

.i List of Bases Changes for Units 2 and 3 t

Unit 2 Unit 3 Revision

{

(Section/Page/ Text)

(Section/Page/rext)

(Alfected Unit / Text).

l 47 3.3/4.3 Bases 3.3/4.3 Bases Revise Unit 2 to match Unit 3.

d

)

g Page 3.3/4.3-18, Arst paragraph, second sentence -

Page 3.3/4.3-18, Afst paragraph, second sentence -

j These include Oyster Creek, Monticello, Dresden 2 and These include Oyster Creek, Monticello, Dresden 2, Dresden 3.

and Dresden 3.

I i

48 3.3/4.3 Bases 3.3/4.3 Bases Revise Unit 3 to match Urut 2.-

i

?

Page 3.3/4.3-18, fourth paragraph, Hrst sentence -

2.

The dirt load is primarily released during STARTUP

2. The dirt load is primarily released during startup of of the reactor when the.

the reactor when the.

49 3.3/4.3 Bases 3.3/4.3 Bases Revise Unit 3 to match Unit 2.

l t

v Page 3.3/4.3-18, fourth paragraph, last sentence -

Page 3.3/4.3-18, fourth paragraph, last sentence -

This preoperational and STARTUP testing is sufficient This preoperational and startup testing is sufficient to l

to detect anomalous drive performance.

detect anomalous drive performance.

-I i

i 3

f i

15 -

(t tndes - os31)

I f

f

=

'I L

Technical Specification Change 370

.I l

List of Bases Changes for Units 2 and 3 i

Unit 2 Unit 3 Revision (Section/Page/ Text)

(Secton/Page/ Text)

(Affected Unit / Text) 50 3.3/4.3 Bases 3.3/4.3 Bases Revise Unit 2 and Unit 3 as foRows:-

Page 3.3/4.3-20, second paragraph, third sentence -

Page 3.3/4.3-20 second paragraph, third sentence -

One percent reactivity limit is considered safe since an insertion of one percent reachvity into the core would One percent reactivity into the core would not lead to One percent reactivity limit is considered safe since not lead to transients exceedng design condtions of l

transients exceeding design condtions of the reactor an lasertion of the reactivity into the core would not the reactor system _

system.

lead to transients exceedng design conditions of the reactor system.

j i

i 51 3.5 Bases 3.5 Bases Revise Unit 3 to match Unit 2.

t Page 3.5/4.5-24, first paragraph, first sentence -

Page 3.5/4.5-27, Hrst paragraph, first sentence -

l i

Analyses presented in the FSAR* and analyses Analyses presented in the FSAR* and analyses presented in conformance with 10 CFR 50, Appendx K, presented in conformance with 10 CFR 50, Appendx K, demonstrated that the core spray system in demonstrated that the core spray system provides l

f conjunction with two LPCI pumps provides adequate adequate cookng to the core to dissipate the energy j

cooling to the core to dssipats the energy associated associated with the loss-of-coolant accident and to hmit with the loss-of-coolant accident and to limit fuel dad fuel dad temperature to below 2,200* F which assures temperature to below 2,200* F which assures that core that cose geometry remains intact and to kmit the core j

geometry remains intact and to limit the core average average dad metal-water reaction to less than 1 i

dad metal-water reaction to less than 1 percent percent l

r i

52 3.5 Bases 3.5 Bases Revise Unit 2 to match Unit 3.

i Page 3.5/4.5-24, first paragraph, second sentence -

Page 3.5/4.5-27, Hrst paragraph, second sentence -

l Core spray distribution has been shown in tests of Core spray distribution has been shown in tests of -

l systems similar to design to BFNP to exceed the systems similar in design to BFNP to exceed the minimum requirements.

minimum requirements

-l l O ttwas -os3t) i l

6 1

.x

9 Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Secton/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) 53 3.5 Bases 3.5 Bases Revise Unit 2 to match Unit 3.

Page 3.5/4.5-30, first paragraph, first sentence -

Page 3.5/4.5-33, second paragraph, first sentence -

The emergency core coohr' J system LOCA analyses for The emergency core cooling system LOCA analyses for small hne breaks assumed Jiat four of the six ADS small tine breaks assumed that four of the six ADS valves were operable.

valves were OPERABLE.

54 3.5 Bases 3.5 Bases Revise Unit 3 to match Unit 2.

Page 3 5/4.5-30 Section 3.5.H. -

Page 3.5/4.5-33 Section 3.5.H. -

3.5.H. Maintenance of Fined Discharae Pioe H. Maintenance of Filled Discharoe Pipe 55 3.5 Bases 3.5 Bases Revise Unit 2 to match Unit 3.

l Page 3.5/4.5-32, first paragraph, last sentence -

Page 3.5/4.5-35, first paragraph, last sentence -

A 6-hour time period to achieve this condition is justified A six-hour time period to achieve this condit:on is since the additional.

justfied since the additional.

56 3.5 Bases 3.5 Bases Revise Unit 2 to match Unit 3.

Page 3.5/4.5-32, third paragraph, first sentence -

Page 3.5/4.5-35, third paragraph, first sentence -

Because the probabihty of thermal-hydraulic oscillations Because the probabihty of thermal-hydraulic osediations is lower and the margin to the MCPR safety hmit is is lower and the margin to the MCPR safety limit is greater in Region li than in Region I of figure 3.5.M-1, greater in Region 11 than in Region i of Figure 3.5.M-1, an immediate scram upon entry into the region is not an immediate scram upon entry into the region is not necessary.

necessary.

-U-(11/W95 - 06.31)

I Technical Specification Change 370 t

List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Section/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) 57 3.6/4.6 Bases 3.6/4.6 Bases Revise Unit 2 and Unit 3 as follow:

Page 3.6/4.6-30, second paragraph, first sentence -

The two gpm hmit for coolant leakage rate increases over any 24-hour period is a limit specified by the NRC The 2 gpm limit for coolant leakage rate increases over The two gpm limit for coolant leakage rate increase (Reference 2),

any 24-hour period is a limit specified by the NRC over any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period is a limit specified by the NRC (Reference 2).

(Reference 2).

58 3.6/4.6 Bases 3.6/4.6 Bases Revise Unit 3 to match Unit 2.

l Page 3.6/4.6-30, sixth paragraph. first sentence -

Page 3.6/4.6-30, sixth paragraph, first sentence -

To meet the safety basis,13 relief valves have been To meet the safety basis,13 rehef valves have been installed on the unit with a total capacity of 84.1 percent installed on the unit with a total capacity of 83.77 of nuclear boiler rated steam flow.

percent of nuclear boiler rated steam flow.

I 59 3 6/4.6 Bases 3 6/4.6 Bases Revise Unit 3 to match Unit 2.

Page 3.6/4.6-30, eighth paragraph, first sentence -

Experience in relief valve operation shows that a testing Experience in relief and safety valve operaton shows of 50 percent of the valves per year is adequate to that a testng of 50 percent of the valves per year is detect failures or deteriorabons.

adequate to detect failures or deteriorations.

}

t I

- ts -

(11/t4/95 - oest)

Technical Specification Change 370 List of Bases Changes for Units 2 and 3 1.

Unit 2 Unit 3 Revision L

(Section/Page/ Text)

(Affected Urut/ Text) 60 3.6/4.6 Bases 3.6/4 6 Bases Revise Unit 3 to match Unit 2.

Page 3.6/4.6-30, eighth paragraph, second sentence -

The rehef valves are benchtested every second The relief and safety valves are benchtested every operating cycle to ensure that their setpoints are within second operating cyde to ensure that their setpoints the 11 percent tolerance.

are within the 11 percent tolerance.

61 3.6/4.6 Bases 3.6/4.6 Bases Revise Unit 2 to match Unit 3.

Page 3.6/4.6-31, References -

Page 3.6/4 6-31, References -

2. Amendment 22 in response to AEC Question 4.2 Unit 3 does not list the reference listed in Unit 2.

of December 6,1971.

62 3.6/4.6 Bases 3.6/4.6 Bases Revise Unit 3 to match Unit 2.

l Page 3.6/4.6-31 References -

Page 3.6/4.6-31, References -

5. Generic Reload Fuel Application, Licensing Unit 3 does not list the reference listed in Unit 2.

Topical Report, NEDE-24011-P-A and Addenda 63 3.6/4.6-32 Bases 3.6/4 6-32 Bases Revise Unit 2 to match Unit 3.

Page 3 6/4.6-32, fourth paragraph, first sentence -

Page 3.6/4.6-32, fourth paragraph, first sentence -

Requinng at least one recirculation pump to be Requiring at least one recirculation pump to be operable while in the RUN mode (i.e., requiring a OPERABLE while in the RUN mode (i.e., requiring a manual scram if both recirculation pumps are tripped).

manual scram if both recirculation pumps are tripped).

. (11/14.95 - os.31) i

9 Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Section/Page/ Text)

(Section/Page/ Text)

(Affected Uni +JText) 64 3.6/4.6-32 Bases 3.6/4.6-32 Bases Revise Unit 2 to match Unit 3.

Page 3.6/4.6-32, fifth paragraph, first sentence -

Requinng the discharge valve of the lower speed loop Requiring the discharge valve of the lower speed loop to remain closed unal the speed of the faster pump is to remain closed untl the speed of the faster pump is below 50 % of its rated speed.

below 50 percent of its rated speed.

O 3.6/4.6 Bases 3.6/4 6 Bases Revise Unit 2 to match Unit 3.

Page 3.6/4 6-33, sixth paragraph -

Page 3 6/4.6 The speciel surveillances implemented as a result of the 1975 fire were not applicable to Unit 3. However, An augmented inservice survelliance program is This Unit 2 paragraph is not in the Unit 3 technical Amendment 206 to the Unit 2 Tech Specs deleted required to determine whether any stress corrosion specifications.

Section 4.6.G.3 which required the augmented has occurred in any stainless steel piping, stainless inservice inspections. The secton shown for the unit 2 components, and highly-stressed alloy steel such Tech Specs should have been deleted by mendment as hanger springs, as a result of environmental 206.

conditions associated with the March 22,1975 fire.

66 3 6/4 6 Bases 3.6/4.6 Bases Revise Reference 1 for both Unit 2 and Unit 3 as follows:

Page 3.6/4.6-33, References -

Page 3 6/4.6-33 References -

1. BFNP FSAR Subsecton 4.12, inservice inspecton

1. Inservice inspection and Testing (BFNP FSAR

1. Inservice inspection and Testing (BFNP FSAR and Testng.

Subsection 4.12)

Subsection 4.12) (1tri4/9s - 0631)

f Technical Specification Change 370 List of Bases Changes for Units 2 and 3 i

Unit 2 Unit 3 Revision (Section/Page/ Text)

(Secton/Page/ Text)

(Affected Unit / Text) 67 3.6/4.6 Bases 3.6/4.6 Bases Revise Unit 2 to match Unit 3.

Page 3 6/4 6-33, References -

Page 3.6/4.6-33, References -

The Unit 2 special instructions implemented as a result of the 1975 Are were not applicable to Unit 3.

5. Mechanical Maintenance instruction 44 Unit 3 does not list reference 5 listed in Unit 2.

However, Amendment 206 to the Unit 2 Tech Specs (Mechanical Equipment, Concrete, and deleted Section 4.6 G.3 which required these special Structural Steel Cleaning Procedure for Residue instructions. Reference 5 shown for the Unit 2 Tech From Plant Fire - Units 1 and 2)

Specs should have been deleted by Amendment 206.

68 3.6/4.6 Bases Page 3.6/4.6-33 References -

Revise Unit 2 to match Unit 3.

Page 3.6/4.6-33, References -

Unit 3 does not list reference 6 listed in Unit 2.

The Unit 2 sr,;ecial instructions implemented as a result of the 1975 fire were not applicable to Unit 3.

4. Mechanical Maintenance Instruction 53 However, Amendment 206 to the Urvt 2 Tech Specs (Evaluation of Corrosion Damage of Piping deleted Section 4.6.G.3 which required these special Components Which Were Exposed to Residue instructions. Reference 6 shown for the U 2 Tech From March 22,1975 Fire)

Specs should have been deleted by nt 206.

69 3 6/4.6 Bases Page 3.6/4.6-33, References -

Delete reference 7 from the 3.6/4.6 Bases for Unit 2.

Page 3.6/4.6-33, References -

Unit 3 does not list reference 7 listed in Unit 2.

7. Plant Safety Analysis (BFNP FSAR Subsection 4.12)

I I (1tness - os:31)

=.

I

'I Technical Specification Change 370.

t List of Bases Changes for Units 2 and 3 i

Unit 2 Unit 3 Revision

' Sechon/Page/ Text)

(Affected Unit / Text) l (Sechon/Page/ Text)

(

70 3.7/4.7 Bases 3.7/4.7 Bases Revise Unit 3 to match Unit 2.

V Page 3.7/4.7-26, third paragraph. second sentence -

Page 3.7/4.7-25, second paragraph. second sentence -

The actions required by Specifications 3.7.C. - 3.7.F.

The achons required by Specifications 3.7.C.-3.7.F.

I assure the reactor can be depressurized in a bmely assure the reactor can be depressurized in a timely

' i manner to.

manner to.

71 3.7/4.7 Bases 3.7/4.7 Bases Revise Unit 2 to match Unit 3.

Page 3.7/4.7-26, fourth paragraph. first sentence -

Page 3.7/4.7-26, third paragraph. Grst sentence -

Should it be necessary to drain the suppression Should it be necessary to drain it'e suppression f

chamber, this should only be done when there is no chamber, this should only be done when there is no

{

requirement for core standby cooling systems requirement for Core Standby Cooling Systems OPERABlWTY.

OPERABluTY.

l I

i 72 3.7/4.7 Bases 3.7/4.7 Bases Revise Unit 2 and Unit 3 as follow.

I Page 3.7/4.7-26, fifth paragraph, first sentence -

Page 3.7/4.7-26, fourth paragraph, Grst sentence -

Umiting suppressaon pool temperature

. and j

ensures margin for complete condensation of steam Umrbng suppression pool temperature.. and ensures Umiting suppression pool temperature..and from the design basis loss-of-coolant accident margin for complete condensation of steam from the assures margin for complete condensation of steam (LOCA).

f design basis LOCA.

from the design basis loss-of-cociant accident.

I i

i i

I I

. mnas-osan.

i.

t

.J c -

2.

L Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3

. Revision (Secton/Page/ Text)

(Secton/Page/ Text)

(Affected Unit / Text) 73 3.7/4.7 Bases 3.7/4.7 Bases Revise Unit 3 to match Unit 2.

Page 3.7/4.7-26, sixth paragraph, second sentence -

Page 3.7/4.7-25, Afth paragraph, second sentence -

1 This acbon would include: (1) use of all available This action would include: (1) use of all available I

means to close the valve, (2) initate suppression pool means to close the valve; (2) inidate suppression pool I

water cooling heat exchangers, (3) initiate reactor water cooling heat exchangers; (3) initiate reactor j

shutdown, and (4)if other relief valves are used to shutdown; and (4)if other relief valves are used to i

depressurize.

depressurize..

l i

t 74 3.7/4.7 Bases 3.7/4.7 Bases.

Revise Unit 3 to match Unit 2.

i Page 3.7/4.7-26, seventh paragraph, Arst sentence -

Page 3.7/4.7-25, sixth paragraph, Arst sentence -

f If a LOCA were to occur when the reactor water if a loss-of-coolant accident were to occur when the temperature is below.. permissible pressures even if reactor water temperature is below... permissible no condensation were to occur.

pressure, even if no condensation were to occur.

l j

t 75 3.7/4.7 Bases 3.7/4.7 Bases Revise Unit 2 to match Unit 3.

'I I

Page 3.7/4.7-27, Arst line -

Page 3.7/4.7-26, Arst line -

r in conjunction with the Mark I containment Short Term In conjuncbon with the Mark i Containment Short Term i

Program, a plant unique analysis.

Program, a plant-unique analysis.

I i

2

[

i.;

f r

E mness -os.sn i

1 t

L"

._.________.____________m.,

~

..r 1

Technical Specification Change 370 f

List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision 5

(Sechon/Page/ Text)

- (Section/Page/ Text)

(Affected Unit / Text)

. 76 3.7/4.7 Bases 3.7/4.7 Bases Revise Unit 3 to match Unit 2.

t i

Page 3.7/4.7-27, second paragraph, first sentence -

Page 3.7/4.7-26, second paragraph, first sentence -

I The relativity smaH containment volume.. limited (a-The relativity sman containment volume.. hmited (a percent or so) reaction of the zirconium and steam percent or so) reaction of the zirconium and steam during a LOCA could lead to the.

during a loss-of-coolant accident could lead to the,

i

.i k

77 3.7/4.7 Bases 3.7/4.7 Bases Revise Unit 3 to match Unit 2.-

l Page 3.7/4.7-27, second paragraph, last sentence -

Page 3.7/4.7-26, second paragraph, last sentence -

The <4 percent hydrogen concentration rninimizes the The <4 percent hydrogen concentration minimizes the

{

possibihty of hydrogen combustion foRowing a LOCA.

possibikty of hydrogen combuston foNowing a loss-of.

coolant accider.t.

f 78 3.7/4.7 Bases 3.7/4.7 Bases Revise Unit 3 to match Unit 2.

Page 3.7/4.7-27, third paragraph, first sentence -

Page 3.7/4.7-26, third paragraph, first sentence -

s The occurrence of.. occurrence of the LOCA upon The occurrence of.. occurrence of the loss-of-I i

which the specified oxygen concentration Smit is based.

coolant accident upon which t:)e specified oxygen concentration krrut is based i

t

.i i (1in4/95 - 0s31)

{

i

'l

t Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Section/Page/ Text)

(Sechon/Page/ Text)

(Affected Unit / Text) 79 3.7/4.7 Bases 3.7/4.7 Bases Revise Unit 2 and Unit 3 as fol!ows:

l Page 3.7/4.7-27 fourth paragraph, third sentence -

Page 3.7/4.7-26. fourth paragraph, third sentence -

Following a LOCA, the Containment Air Monitoring (CAM) System continuously monitors the hydrogen Following a LOCA the Containment Air Monitoring Following a loss-of-coolant accident the Containment concentration of the containment volume. Two (CAM) System continuously monitors the hydrogen Air Monitoring (CAM) System contmuously monitors the independent systems are capable of sampling and concentration of the containment volume. Two hydrogen concentration of the containment volume.

monitoring hydrogen concentratson in the drywell and independent systems (a system consists of one Two independent systems (a system consists of one the torus. Each sensor and associated circuit is hydrogen sensing circuit) are instal:ed in the dryweu hydrogen sensing circuit) are installed in the drywell periodically checked by a calibration gas to verify and the torus. Each sensor and associated circuit is ant' the torus. Each sensor and associated circuit is operation. Failure of one system does not reduce the periodically checked by a calibration gas to verify periodically checked by a calibration gas to verify abihty to monitor the hydrogen concentration in the operation. Failure of one system does not reduce the operation. Failure of one system does not reduce the drywell or torus atmosphere as a second independent ability to monitor system atmosphere as a second ability to monitor system atmosphere as a second and redundant system will still be OPERABLE.

independent and redundant system will still be independent and redundant system will still be OPERABLE.

OPERABLE.

I

- 25 (114445-0631)

Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Sechon/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) 80 3.7/4.7 Bases 3.7/4.7 Bases Delete the paragraph in Unit 2 and Unit 3 - Does not agree with FSAR 5.2.6.

Page 3.714.7-28, first paragraph -

Page 3.7/4.7 27, first paragraph -

In terms of separabelity, redundancy for a failure of the in terms of separabihty, redundancy for a failure of the torus system is based upon at least one OPERABLE torus system is based upon at least one OPERABLE drywen system. The drywen hydrogen concentration drywell system. The drywell hydrogen concentration can be used to kmit the torus hydrogen concentrabon can be used to limit the torus hydrogen concentration during post-1.OCA condtions. Post 4 OCA calculatrons during post-loss-of-coolant accident condtions. Post-show that the CAD system initiated within two-hours at loss-of-coolant accident calculations show that the CAD a flow rate of 100 scfm wiR limit the peak drywen and system within two hours at a flow rate of 100 scfm wiu wetwell hydrogen concentration to 3.6-percent (at 4 limit the peak drywen and wetweR hydrogen hours) and 3.8-percent (at 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months ), respectively. This concentration to 3.9-percent (at 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ) and 3.9-is based upon purge initation after 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months at a flow percent (at 32 hour3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months sh respecbvely. This is based upon rate of 100 scfm to maintain containment pressure purge initiation after 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months at a flow rate of 100 scfm below 30 psig. Thus, peak torus hydrogen to maintain containment pressure below 30 psig. Thus, concentration can be controHed below 4.0 percent using peak torus hydrogen concentration can be controued either the drect torus hydrogen monitoring system or below 4.0 percent using either the drect torus hydrogen

~i the drywell hydrogen monitoring system with monitoring system or the dryweg hydrogen monitoring appropriate conservatism ($ 3.8-percent), as a guide system with appropriate conservabsm ($ 3 9-percent),

for CAD / Purge operations.

as a guide for CAD / Purge operations.

89 3.7/4.7 Bases 3.7/4.7 Bases Revise Unit 3 to match Unit 2.

Page 3.7/4.7-35, fourth paragraph -

Page 3.7/4.7-34, fourth paragraph -

Group 7 - (Deleted)

Group 7 -Process lines are closed only on the respective turbine steam supply valve not fully closed. This assures that the valves are not open when HPCI or RCIC action is required. (11/14/95 31)

Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Secton/Page/ Text)

(Sechon/Page/ Text)

(Affected Unit / Text) 82 3.9 Bases 3.9 Bases Revise Unit 2 and Unit 3 as follows:

Page 3 9/4 9-19, first paragraph, first sentence -

Page 3 9/4.9-18, first paragraph, first sentence -

The objective of this specification is to assure an adequate source of electrical power to operate facilities The objective of this specificaton is to assure an The objective of this specification is to assure an to cool the units during shutdown and to operate the adequate source of electrical power to operate facilities adequate source of electrical power to eperate facilites engineered safeguards following an accident.

to cool the plant during shutdown and to operate the to cool the unit during shutdown and to operate the engineered safeguards following an accident.

engineered safeguards following an accident.

83 3.10 Bases 3.10 Bases Revise Units 1,2, and 3 as fo"ows:

Page 3.10/4.10-12 second paragraph, last sentence -

Page 3.10/4.10-11, second paragraph, last sentence -

3.10 Bases The 4004b load-trip setting on these hoists is adequate The 4004b load-trip setting on these hoists is adequate Page 3.10/4.10-12, second paragraph, last sentence -

to trip the interlock when one of the more than 6004b to trip ihe interlock when one of the more than 6004b fuel bundes is being handed.

fuel bundes is being handled.

The 4004b load-trip setting on these hoists is adequate to inp the interlock when one of the more than 5504b fuel bundles is being handled.

l 84 3.10 Bases 3.10 Bases Revise Unit 3 to match Unit 2.

l Page 3.10/4.10-13, fourth paragraph, last sentence -

Page 3.10/4.10-12, fourth paragraph, last sentence -

I Control rods in cells from which all fuel has been Centrol rods in cells from which all fuel has been removed.and which are outside the periphery of the removed may be armed electrically and moved for then existing fuel matrix may be armed electrically maintenance purposes during full core removal, and moved for maintenance purposes during full core provided all rods that control fuel are fully inserted and removal, provided all rods that control fuel are fu'!y electrically disarmed.

inserted and electrically disarmed. (11/14,95 - o6.31)

t Technical Specification Change 370 List of Bases Changes for Units 2 and 3 Unit 2 Unit 3 Revision (Secton/Page/ Text)

(Section/Page/ Text)

(Affected Unit / Text) 85 3.10 Bases 3.10 Bases Revise Unit 3 to match Unit 2.

Page 3.10/4.10-14, fourth paragraph -

Page 3.10/4.10-13, fourth paragraph -

D. Reactor Buildina Crane The reactor building 3.10.DI4.10.D Bases Reactor Buildino Crane The crane and 125-ton.

reactor building crane and 125-ton.

86 3.10 Bases 3.10 Bases Revise Unit 3 to match Unit 2.

Page 3.10/4.10-14, seventh paragraph -

Page 3.10/4.10-13, seventh paragraph -

E. Spent Fuel Cask The spent fuel cask design.

3.10.E14.10.E Spent Fuel Cask The spent fuel cask design.

87 3.10 Bases 3.10 Bases Revise Unit 2 to match Unit 3.

l I

Page 3.10/4.10-15, page btle -

Page 3.10/4.10-14, page htle -

Unit 2 does not have a btle.

3.10 BASES (Contd)

-2s-(1 tit 4ss -osas;

]

.

ML20094M759

Contents

Text

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

Navigation menu

ML20094M759

Text

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

1.1 Bases

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