ML20094B316

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Forwards Addl Info Re Conformance w/post-accident Sampling Sys Criteria 2 & 10,per TMI Item II.B.3.Core Damage Assessment Procedure Based on C-E Owners Group Guidelines Will Be Submitted by 841231
ML20094B316
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 10/30/1984
From: Lundvall A
BALTIMORE GAS & ELECTRIC CO.
To: John Miller
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM NUDOCS 8411070102
Download: ML20094B316 (9)


Text

7" BALTIMORE GAS AND ELECTWIC CHARLES CENTER.P.O. BOX 1475 BALTIMORE, MARYLAND 21203 October 30,1984 ARTHun E. LUNDVALL. JR.

vice petsiotw SuprLv Director of Nuclear Reactor Regulation Attention: Mr. 3. R. Miller, Chief Operating Reactors Branch //3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Calvert Cliffs Nuclear Power Plant Units Nos.1 & 2; Docl<ets Nos. 50-317 and 50-318 NUREG-0737 Item II.B.3, Post Accident Sampling System

References:

1. NRC Memorandum from W. Johnston to G. Lainas, " Safety Evaluation of Post-Accident Sampling System of Calvert Cliffs Nuclear Power Plant," dated June 24,1983.
2. Combustion Engineering Report CE-NPSD-241, " Development of Comprehensive Procedure Guidelines for Core Damage Assessment," dated July 1983.

Gentlemen:

At your request, the following additional information is provided to assist you in your review of the Calvert Cliffs post-accident sampling system regarding conformance with system criteria #2 and #10 as evaluated in Reference 1:

Criterion 2 A core damage assessment procedure based on the generic guidelines developed for the CE Owners Group (Reference 2) is being written for Calvert Cilffs.

We will submit a copy of the completed procedure for your information by December 31,1984.

Criterion 10 The attached excerpts from the Calvert Cliffs Post-Accident Sampling System Technical Manual (Combustion Engineering Report CENTM-14) Indicate the post-accident environmental conditions for which the system was designed.

Also shown are the accuracles and ranges specified for the boron meter, the pH meter, the reactor coolant hydrogen meter and the oxygen meter.

Periodic system operability testing and operator refresher training will be performed in accordance with the technical specification proposed in our license amendment request dated June 29,1984.

hhc ONO p

i \\

w Mr. 3. R. Miller October 30,1984 The design of the post-accident sampling system, in conjunction with the procedures and training discussed above, provide reasonable assurance that the system will be available when required.

I If you should have any questions concerning these matters, please do not hesitate to contact us.

Very truly yours, 656 vdW&m AEL/BSM/vf

\\

Attachment cc: D. A. Brune, Esq.

G. F. Trowbridge, Esq.

Mr. D. H. Jaffe, NRC Mr. T. Foley, NRC

Messrs. A. E. Lundvall, Jr.

- bcc:

V. F. Stricklin (3)

3. A. Tiernan C. H. Cruse R. E. Denton P. T. Crinigan
3. M. Moreira R. F. Ash
3. M. Dahlquist, 3r.

R. C. L. Olson

' R. P. Helbel T. E. Forgette

3. F. Shire B. S. Montgomery M. T. Navin -

e

(

)

1APPENDIXA-ENVIRONMENTALCONDITIONS

' Valva Time After List 5-Event Category Location Condition

_ Temp.

Pressure

. Initiation Humidity Radiation 0

D.

Aux. Bldg.

Post-LOCA 120 F atmospheric 0-4 hrs (a)

(b) 104 F atmospheric 4-24 hrs (a)

(b) 0 C

Normal 60-104 F* atmospheric N/A (a)*

(b)

A Inside Post-LOCA 300 f 60 psig (max) (c) saturated (d)

Containment (max?

steam / air mixture 0

-B Normal 60-120 F 0-5 psig N/A (a)

(e)

Notes:

(a)60-80F: 95% RH 80 F to max, temperature: fixed moisture content equivalent ta 95% RH 0

9 80 F g

Sample Station Control (b)

Reactor Coolant **

Cont. Atnesphere Panel 4

2 Dosa Rate

  • 5x10 R/Hr 9 t= 0 2x10 R/Hr 0 t = 0 3

Decays to *.

5x10 R/Hr 0 t 5 days 20 R/Hr 9 t= 6 days 2

and Decays Further to'.

5x10 R/Hr e t= 40 days 2 R/Hr 9 t = 20 days 5

4 4

Total Integrated Doso 7x10 Rads lx10 Rads 1x10 Rads '

(c)

Environment conditions decay to normal by t=10 days after the event initiation.

8 (d)

Total integrated dose is 10 rads.

7 (e) Total integrated dose is 10 rads.

  • Containment Isolation Valve PS-230 has a specified environmental temperature 0

of 220 F in a saturated steam / air mixture for a period of a week after.a main steamline break,

    • Also applicable to all PASS equipment outside the sample station in the pd auxiliary building.

~00000-PE-5051 rRev. 00 Page 1 of 1

r:

APPENDIX B - CHEMISTRY LIMITS L)

Reactor Coolant Chemistry Limits Parameter Limit pH 3.8-10.6 Hydrazine (N H )

0-50 ppm 24 Ammonia _ (NH )

0-50 ppm 3

Lithium 0-2.5 ppm

~

Dissolved. Hydrogen 0-2000cc(STP) H /kg. H O

~

2 2

Dissolved Oxygen Air Saturated (max)

DissolvedNitrogen 0_100 cc (STP) N /kg H O 2

2 Suspended Solids 0-2 ppm Chloride 0.15 ppm C1 Fluoride 0.1 ppm F Boron 0-5000 ppm B

.?

O 00000-PE-S051 Rev.00 Page 1 of 3 m_

y w

4 -

=-f~~;

Appendix C (cont'd)..

~

Vtrified: Yes x No

-\\

INSTRUMENTATION REQUIREMEtlTS t/ )

A-502 12.

Sensor Working Fluid: Normal Design

1 3 Channel Number Temperature (g)

Pressure (psi 80 100

2. A.hannel Name Boron. Meter tI1 oF) 120 200 Fluid Type Post-Accident Reactor Coolant 3.) Quantity l'

Chemistry Appendix B M System. -Post-Accident Sampling

13. Normal Operating Range 5h P&ID's<

E-PAS-310-152 100-4400 ppm (6)L!nstrumentFunction-

. Indicate Component Parameter Measured Boron Concentration

Parameter. Controlled none On (open Setpoint Above Below Component-(s) Controlled none Off (closed) Setpoint Above
7- ~ Performance
,2% (S.G. Sensitivity Below

= !.000025) 15.

Control (Regulated)

LAccuracy

Response

Component L8. (Location:' Control Remote S/D Local Room-Local Location-(s) Panel A to t ange Auto Setpoint Proportional a ize Integrated Record.

Rate 0-5000 ppm-(measured S.G.=0.98 to 015)16. Pipe Run (size / schedule /end connection).

Linear x

3/8" 0.0. in. / 16 BWG/Swagelok Lo arithm ASME III, Class

-none 7.

Emergency Power none

10. - Alarm / Trip Setpoints:

18.

Requirements for Abnormal Operation:

HH Trip Above Post LOCA Yes x tro L H Trip ' Above Post SLB Yes No x L Trip Below Post Seismic Event Yes.

tio x LL Trip Below

Other Trip Safe-Shutdown Yes tio x
HH Reset Below Other*

H Reset Below' LL Reset Above

19. Other Raquirements: Sample flow rate =,

p LLL Reset Above 1 gpm.; temperature compensation.is L

Other Reset reouired between 800F and 1600F; for illi External Environment (see Appendix AI calibr.0~1200F,~0ppmboron=.9915S.i Sensor Auxiliary Bldg.

~5000 lpm" boron = l'.0017 S.G.

i (relationislinear)'

Norma) and LOCA t,

C ta'.(1) Plant Engineering recommends' a "Dynatrol" specific gravity (S.G.) ' device for this application calibrated to

~ boron concentration in ppm. After initiation of con-tainment sump recirculation, interferring constituents

,will be accounted for by a Plant Engrg, supplied curve.

00000-PE-SD51, Rev. 00 Page 10 of 37

. ~-. - - -

T u--:

^

}

Appendix C-(cont'd)

~

lerified: Yes x

No INSTRUMENTATION REQUIREMENTS

11.. Channel-Number-A-503 12.

Sensor Working Fluid: Normal Desion 2.?> Channel Name-pH~ Meter Pressure (psig) 80 100

~

Temperature (OF) 120 200 Fluid Type Post-Accident Reactor Coolant f3L Ssantity I'

Chemistry Appendix B-c4. jystem.

Post-Accident Sampling 13.

Normal Operating Range I5.: reID's '

E-PAS-310-152 4.5 - 10.0

'6.r. InstrumentL Function Indicate g

ff mp nent

.l Parameter Measured nw On-(openSetpointAbove Parameter Controlled nune Component (s) Controlled-Below nnn.

Off (closed) Setpoint Above

7.

Parformance:

Below 15.

Control (Regulated) n C

oje 8.

Location: Control.

LRemote S/D Local Range p

Room Local Location (s) Panel Automatic Range Indication x

Auto-Setpoint Proportional h' Record ta ize Integrated i

Rate 16.

Pipe Run (size / schedule /end-connection)

Ra 3 -12 3/8" 0.0.in / 16 BWG/Swagelok i

Linear-x Logarithmic ASME III, Class none

. Square Root-none 17.

Emergency Power

10. Alarm / Trip Setpoints:_
18. - Requirements for Abnormal Operation:

HH Trip Above Post LOCA Yes x no

<H Trip Abovei L Trip Below

' Post SLB Yes No y

'LL Trip Below Post Seismic Event Yes

No__x, 0ther Trip Safe Shutdown Yes Noa HH Reset Below Other.

H Reset Below L Reset Above

19. Other Requirements:

Sample

'LL Reset Above flow rate is 1 gpm Other Reset

11. External Environment (see Appendix A)-

Sensor ~

Aux. Building - Normal & LOCA O.

00000-PE-SD51,'Rev. 00 Page 11 of 37

7-

~~

AppendixC(cont'd)~

Verifikd: Yss x No N

' INSTRUMENTATION REQUIREMENTS

~

J 11? Channel Number A-504 12.

Sensor Working Fluid: Normal Desian ressur p$

l2'.

Channel Name Reactor' Coolant Hydrogen e

)

12

  • I Fluid Type *N2, Hg, 07 Fission Products 3.

Quantity 1

Chemistry N/A

4.

System - Post-Accident Sampling 13.

Normal Operating Range

-5.

P&ID's -

E-PAS-310-152 0-100 vol'ee %

'6.

Instrument Function Indicate 14.

Control (on/off or open/ closed) omponent

~ Parameter Measured Volume % H,

. Parameter Controlled none On(openSetpointAbove Component (s) Controlled none Below Off(closed)SetpointAbove 7.

P;rformance:

Below jc "

,[

15.

Control (Regulated)

~

es on Component 8.

Location: Control Remote S/D Local Room Local Location (s) Panel fa ut.a t nge Indication x

Auto Setpoint gmAlann Proportional

' ) Totalize Integrated

~ Record Rate la h-O 9*

16.

Pipe Run (size / schedule /end connection) m 3/8" 0.0. in / 16 BWG/Swagelok Linear x

Logarithmic ASME III, Class none Square Root 17.

Emergency Power ncne

10. Alarm / Trip Setpoints:

18.

Requirements for Abnormal Operaticn:

HH Trip Above Post LOCA Yes X flo H Trip Above Post SLB Yes No y L Trip Below LL Trip Below Post Seismic Event Yes No y Other Trip Safe Shutdown Yes_,__flo y

HH Reset Below Other*

H Reset Below

.L' Reset Above 19.

Other Requirements:

Sample flow rate LL Reset Above is 50-350 cc/ min Other Reset

11. External Environment (see Appendix A)

Sensor Auxiliary Bldg. - Normal & LOCA

~

(O

  • R.H. = 0 - 100%

J 00000-PE-SD51. Rev. 00 Page 12 of 37

y

,.A' Verified: Yes x No Appendix C (cont'd)

INSTRUMENTATION REQUIREMENTS A-505 '

12. Sensor Working Fluid: Normal Desian Channel Number 2.-

Channel Name Oxygen Meter Pressure (psi 5

100 Temperature (

)

120 200 Fluid Type *N2, H. 02. Fission Products 2

3.

Quantity I

Chemistry N/A 4*

System Post-Accident Sampling

13. Normal Operating Range 5,

P&ID's E-PAS-310-152 0-5 Volurie %

.6.

Instrument Function Indicate

14. Control (on/off or open/ closed)

Component Parameter Measured Volume % 0, Parameter Controlled None On(openSetpointAbove Component (s) Controlled None Below Off(closed)SetpointAbove 7.

Performance:

Below

+ 2%

15. Control (Regulated) ra g

Component 8.' Location: Control Remote S/D Local Room Local Location (s) Panel faut tc ange Auto Setpoint

'I

(

o,,"ize Proportional Integrated Record Rate 16.

Pipe Run (size / schedule /end connectior.',

-5 e%

e 3/8" 0.D. in / 16 BWG / Swagelok Linear y

Logarithmic none ASME III, Class Square Root N

U.

Emergency Power

10. Alarm / Trip Setpoints:

18.

Requirements for Abnormal Operation:

HH Trip Above H Trip Above Dost LOCA Yes x No L Trip Below-Post SLB Yes No x LL Trip Below Post Seismic Event Yes No x Other Trip Safe Shutdown Yes No x HH Reset Below Other.

H Reset Below

19. Other Requirements:

Samole flow L Reset Above rate is 50-350 cc/ min LL Reset Above Other Reset 11.

External Environment (see Appendix A)

Sensor Aux. Bldg.- Normal & L0r,(

C)'

  • R.H. = 0-100%

t.

00000-PE-S051, Rev. 00 Page 13 of 37