ML18139C340

From kanterella
Jump to navigation Jump to search
Forwards Response to Generic Ltr 82-28, Inadequate Core Cooling Instrumentation Sys, Per 830310 Ltr.During Upset Conditions,Alarm Functions Provided in Conjunction W/ Subcooling Monitors
ML18139C340
Person / Time
Site: Surry, North Anna, 05000000
Issue date: 05/12/1983
From: Steward W, Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Eisenhut D
Office of Nuclear Reactor Regulation
References
721, GL-82-28, NUDOCS 8305200499
Download: ML18139C340 (19)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261

w. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS May 12, 1983 Mr. Harold R. Denton, Director Serial No. 721 Office of Nuclear Reactor Regulation NO/DWL:acm Attn: Mr. Darrell G. Eisenhut, Director Docket Nos. 50-280 Division of Licensing 50-281 U. S. Nuclear Regulatory Commission 50-338 Washington, D. C. 20555 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY AND NORTH ANNA POWER STATIONS RESPONSE TO GENERIC LETTER 82-28 Enclosed is Vepco's response to Generic Letter 82-28, "Inadequate Core Cooling Instrumentation System" for the Surry and North Anna Power Stations. Per our letter of March 10, 1983 (Serial No. 721A), this response was due on May 9, 1983. Due to last minute preparation difficulties, an additional few days were necessary. Both the Surry and North Anna NRC Project Managers were informed of this delay.

In preparing our response to Generic Letter 82-28, it became necessary to define the usage of certain terms in the information request. Therefore, for the purposes of our response, "additional" ICC instrumentation refers to our Reactor Vessel Level Instrumentation System and "existing" ICC instrumentation refers to our Core Exit Thermocouples and Subcooling Margin Monitor.

8305200499 830512 .

PDR ADOCK 05000280 P PDR

VIROINIA ELECTRIC AND POWER COMPANY TO Harold R. Denton Pursuant to 10CFR50.54(f), the enclosed information is submitted under oath.

~elil~

W. L. Stewart ';:

cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Licensing Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Mr. Milton B. Shymlock NRC Resident Inspector North Anna Power Station Mr. Donald J. Burke NRC Resident Inspector Surry Power Station

RESPONSE TO GENERIC LETTER 82-28 "INADEQUATE CORE COOLING INSTRUMENTATION SYSTEM" APPENDIX Checklist for Plant Specific Review of ICC Instrumentation System For North Anna Power Station Units 1 and 2 Docket No. 50-338/50-339 Surry Power Station Units 1 and 2 50-280/50-281 Operated by: Virginia Electric and Power Co.

P.O. Box 26666 Richmond, Va.

Reference Deviations Schedule

1. Description of the proposed final system including:
a. a final design description of additional instrumentation and displays; l, 4 & 5 No Complete
b. detailed description of existing-----------------

instrumentation systems. 2, 12 No Complete

c. description of completed or planned modifications. _________

3 To Be

_...."""'"............................... Reference 3 Deterroioed

2. A design analysis and evaluation of inventory trend instrumentation, and test data to support design in item 1. 1, 2, 4 through 9 No Complete

~---

3. Description of tests planned and results of tests* completed for evaluation, qualification, and calibration of additional instru-mentation. 6, 7, 8, 9 No Complete
4. Provide a table or description covering the evaluation of con-formance with NUREG-0737: II.F.2, Attachment 1, and Appendix B (to Appendix B Responses be reviewed on a plant specific 1, 2, 10, 14,5 basis)* Attachment 1 Resp. No Complete rr,C: 5* Describe computer, software and display functions associated with ICC monitoring in the plant. 1 & 2,4,5 No Complete Attachment 1 Responses
6. Provide a proposed schedule for installation, testing and cali-bration and implementation of any proposed new instrumentation or To Be information displays. 3, 2 Determined Reference 3

Reference Deviations Schedule

7. Describe guidelines for use of rea.ctor coolant inventory tracking system, and analyses used to develop procedures.
  • 13 No Reference 3
8. Operator instructions in emergency operating procedures for ICC and how these procedures will be Station Abnormal and Emergency modified when final monitoring Procedures. These procedures will be system is implemented. modified to be consistent with WOG recommendations (Reference 13) on the schedule provided by reference 3.
9. Provide a schedule for additional submittals required, None Required per NUREG-0737; Item II.F.2
  • II.F.2 Attachment 1 (for Core Exit Thermocouples)

In response to item 4 in the above checklist, the following materials should be included to show that the proposed system meets the design and qualification criteria for the core exit thermocouple system.

1. Provide diagram of core exit thermocouple locations or reference the generic description if appropriate.

See figures for Attachments A & B

2. Provide a description of the primary operator displays including:
a. A diagram of the display panel layout for the core map and description of how it is implemented, e.g., hardware or CRT display.
b. Provide the range of the readouts.
c. Describe the alarm system.
d. Describe how the ICC instrumentation readouts are arranged with respect to each other.

See Attachment A & B

3. Describe the implementation of the backup display(s) (including the sub-cooling margin monitors), how the thermocouples are selected, how they are checked for operability, and the range of the display.

Included in Reference 2.

e

4. Describe the use of the primary and backup displays. What training will the operators have in using the core exit thermocouple instrumentation?

How will the operator know when to use the core exit thermocouples and when not to use them? Reference appropriate emergency operating guidelines where applicable.

See Attachment A & B

5. Confirm completion of control room design task analysis applicable to ICC instrumentation. Confirm that the core exit thermocouples meet the criteria of NUREG-0737, Attachment 1 and Appendix B, or identify and justify deviations.

The Control Room Design task analysis has not been completed. See Refer-ence 3 for schedule.

6. Describe what parts of the systems are powered from the lE power sources used, and how isolation from non-IE equipment is provided. Describe the power supply for the primary display. Clearly delineate in two categories which hardware is included up to the isolation device and which is not *

.This item is presently being addressed in response to R.G. 1.97. See Reference 3. Reference 2 provides current description.

7. Confirm the environmental qualification of the core exit thermocouple instrumentation up to the isolation device.

The environmental qualification of the core exit thermocouples including the reference junction box will be addressed in response to R.G. 1.97. See Reference 3.

Confirm explicitly the conformance to the Appendix B items listed below for the ICC instrumentation, *.i.e., the SMM, the reactor coolant inventory tracking system, the core exit thermocouples and the display systems.

Reactor Coolant Inventory Reference Deviations

1. Environmental qualification 14 None
2. Single failure analysis 10 None
3. Class lE power source 2 None Proposed Availability prior to an accident T.S.; 1 of 2 channels operable
5. Quality Assurance Yes[per Appendix B .10CFR50] None
6. Continuous indications Yes None

Reactor Coolant Inventory Reference Deviations

7. Recording of instrument outputs Yes [single train] None
a. Identification of instruments 4 None
9. Isolation 2 None Appendix B (of NUREG-0737, II.F.2)

Confirm explicitly the conformance to the Appendix B items listed below for the ICC instrumentation, i.e., the SMM, the reactor coolant inventory tracking system~ the core exit thermocouples and the display systems.

SMM Reference Deviations

1. Environmental qualification 3*
2. Single failure analysis 3*
3. Class IE power source 3*
4. Availability prior to an accident I of 2 Channels Operable
5. Quality Assurance Yes
6. Continuous indications Yes
7. Recording of instrument outputs Yes
8. Identification of instruments 2
9. Isolation 2
  • Will be addressed in Response to RG.1.97.

e e Appendix B (of NUREG-0737, II.F.2)

Confirm explicitly the conformance to the Appendix B items listed below for the ICC instrumentation, i.e., the SMM, the reactor coolant inventory tracking system, the core exit thermocouples and the display systems.

Core Exit Thermocouples Reference Deviations

1. Environmental qualification 3*
2. Single failure analysis 3*
3. Class IE power source 3*
4. Availability prior to an accident 1 of 2 Operable**
5. Quality Assurance Yes**
6. Continuous indications Yes**
7. Recording of instrument outputs Yes
8. Identification of instruments 2
9. Isolation 2**
  • Will be addressed in Response to RG.1.97.
    • Input to SMM portion only.
    • For the users of either Combustion Engineering Heated Junction Thermocouple (HJTC) System or Westinghouse Differential Pressure (dp) system a detailed response to the plant specific items stated below should be provided.

Reference Deviations A. Westinghouse dp System

1. Describe the effect of instrument uncertainties on the measurement of level. 1, 4 5 None

¥' *

2. Are the differential pressure transducers located outside .:.

containment? Yes None

3. Are hydraulic isolators and sensors included in the impulse lines. Yes None

REFERENCES (1) VEPCO Letter to NRC dated November 6, 1981; S/N 623 (2) VEPCO Response to NUREG 0737 POST TMI REQUIREMENTS Rev O through Rev 3 dated December 15, 1980 (3) VEPCO Letter to NRC dated April 15, 1983; S/N 006 (4)

SUMMARY

REPORT Westinghouse Reactor Vessel Level Instrumentation System for Monitoring Inadequate Core Cooling December, 1980.

Submittal letter T. M. Anderson (W) to Darrell G. Eisenhut (NRC)

NS-TMA-2358 of December 23, 1980 (5) VEPCO Letter to NRC dated November 6, 1981; S/N 622 (6) SUPPLEMENTARY INFORMATION Submittal Letter E. P. Rahe (W) to L. E. Phillips (NRC)

MS-EPR-2579 of March 19, 1982

- (7) W EVALUATION OF TESTS S-UT-3, S-UT-6, S-UT-7, S-NC-2, S-NC-3, S-NC-8 Submittal Letter E. P. Rahe (W) to L. E. Phillips (NRC)

NS-EPR-2526 of December 9, 1981 (8) W EVALUATION OF TEST S-UT-8 Submittal Letter E. P. Rahe (W) to L. E. Phillips (NRC)

NS-EPR-2542 of January 13, 1982 (9) W EVALUATION OF TEST S-lB-1 AND FUNCTIONAL TEST Submittal Letter E. P. Rahe (W) to L. E. Phillips (NRC)

SED-SA-0081 of June 28, 1982

'J!"r.C:

(10) RESPONSE TO REQUEST TO WOG FOR ADDITIONAL INFORMATION Submittal Letter E. P. Rahe (W) to Dennis M. Crutchfield (NRC) NS-EPR-2597 of May 14, 1982

e

.References Continued:

(11) Reference Deleted

  • (12) RELEVANT DRAWINGS OF EXISTING INSTRUMENTATION SYSTEMS North Anna UFSAR Chapter 7 - Core Cooling Inst., Thermocouples Surry UFSAR Chapter 7 ~ Thermocouples, Subcooling Monitor Inst.

North Anna UFSAR Chapter 5 --itCS Flow Diagram Surry UFSAR Chapter 4 - RCS Flow Diagram (13) Critical safety function status trees for core cooling and system inventory volumes 1, 2, and 3 Emergency Response Guidelines (ERG) Developed by Westinghouse Owner's Group (WOG) Sections FR-C.l and C.2, FR-I.3, FR-P.l Refer also E20.26 (which is a new section to be added, for natural circu-lation cooldown regarding depressurization in the upper head. Although this shows the use of the RVLIS instrumentation, it is not specifically for inadequate core cooling (ICC) monitoring.

Volume 1 and 2 was under cove~ of OG-64, 11/30/81 O. Kingsley (WOG) to D. Eisenhut (NRC)

Volume 3 was under cover of OG-83, 1/4/83 O. Kingsley (WOG) to D. Eisenhut (NRC)

All member utilities received copies under cover of letters:

WOG-81-235, 12/2/81 WOG-83-100, 1/4/83 (14) ENVIRONMENTAL QUALIFICATION (Note Various Equipment Data Qualification Packages) -

i.e., EQDP - for RVLIS instrumentation are submittals as supplements to the Environmental Qualification topicals WCAP-8587, non-proprietary (which provides summary EDQP's) and WCAP-8687, proprietary (which provides de-tailed EDQP's).

  • EQDP References are as follows:
1. ESE-4 D/P Transmitters Outside Containment - Previously submitted (Note, this EQDP does not specifically reference transmitters to

~~

2.

RVLIS, but this will be done)

ESE-48 High Volume Pressure Sensor Submitted on 2/28/83

3. ESE-49 Hydraulic Isolator Submitted on 2/28/83
4. ESE-42 Strap-on RTD's Submitted on 2/28/83
s. ESE-66 Remote Digital Displays (MCR) To Be Supplied By~-
6. ESE-67 Micro (Jc.) Processor To Be Supplied By~-
1. ESE-50 Entire RVLIS Package To Be Supplied By~-

e ATTACHMENT A Page 1 of 5 ADDITIONAL INFORMATION IN RESPONSE TO THE REQUIREMENTS OF NUREG-0737: II .F. 2 ATTACHMENT 1 - NORTH ANNA POWER STATION 2 (a) See attached pages. These are examples of the printout display that is available to the Control Room Operator on demand.*

(b) The range of all T/C printout locations available' to the operator is 0° F to 1700°F. The range of input and readout to the subcooling monitor is 0° F to 2300° F.

(c) There are no alarms associated with the incore thermocouple during normal operation. This system is used in conjunction with the flux monitoring system for power distribution. During upset conditions, the alarm functions are provided in conjunction with the Subcooling Monitors. In . addition, the incore T/C input to the computer has a "computer alarm" that actuates at 700° F.

Trend capability is available on demand by the establishment of a trend block. Future trending capability is being considered for the SPDS. See Reference 3. There is an automatic initiation of an incore thermocouple digital display that occurs on a reactor trip (both trip breakers open) and with RCS temperature greater than 550° F. This printout is displayed on the utility typewriter on the computer console and is updated every 2 minute_s and printed in T/C sequence.

If the RCS temperature drops below 550° F, the computer output would continue for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. After this time, the printout would be obtained manually. Therefore, the Control Room Operator or Shift Technical Advisor has the. capability for tending the incore thermocouples.

(d) Reference 3 addresses review of ICC instrumentation readout arrange-ments.

e ATTACHMENT A Page 2 of 5 GENERIC LETTER 82-28 Additional information

  • II.F.2 Attachment 1 (for Core Exit Thermocouples) 4 The post-TMI requirements for the upgrading of Reactor Operator training programs included specific training topics on the use of the primary and back-up displays for the Incore Thermocouples. Since this initial training was completed, a retraining program was included to ensure proficiency in this area.

The emergency procedures were revised to provide for more closely monitoring the incore T/C's for the evaluation of core conditions. These procedures will be upgraded further based on the WOG recommended guidelines presently under development. See Reference 3.

  • r:,,

..... tV 1,0. * .&L.t*

POOT LEVEL IS DROPPING Ul*""\.*I 114 ,4 I.._-., 1..,11 I l/1 U 111 I Ill I.* v 11.*I* 11111 v I *. , ....

REACTOR COOLENT LEA~-RATE rROGRAM STOrP[D VRA THERftOCOUPLE AND FUEL ASSEMBLY POWER OUTPUT

SUMMARY

  • b+54 DATE: 4/22/83 TlftE START 9;52. B UP TO 9;53. 6

~ 'i 32 ..~ ~II.ff 1

n POWER 2851). 6 M'H BORON CONCENTRATION ROD POSITION:

f;F,,1 SBB Cr.A c:BB CP..C CBD F*L 228 228

  • 228 * ..
  • 228 .. 228
  • 223-*-- -* i:30 REACTOR LOOP A VARIABLES:

T-1~ TAVGl TAVG2 TOTI TDT2* FLOWl FLOW2 FLON3 549.7 580.5 580.7 100.7 100.9 98.4 100.2 100.9 REACTOR LOOP 8 VARIABLES I * * *-----

1-JN. 1AVG1 TAVG2 , TDT1 TDT2 FLOWl FLOW.? FLOW3 549.5 579.8 579.6 98.1 99.

99.B 96;9 101;4 e

6 REACTOR LOOP C ~ARIABLES l;-JH TAVG1 TAVG2- lDl1 ** HJTi1 *FlOW1 ** FLOW2 - FLOW3 -*** --- *** -***-**- ***

  • 549.3 580.5 581.2 101.6 103.0 99.5 100.5 99.6 SYSTlM PRESSURE
  • 2249.6 AVERAGE INCORE T/C TEMPERATURE: 606.7 INDIVIDUAL JNCORE 1/C TEMPERATURES <IN ASCENDING ORDERJ:
  • 50,. J 567 .5 589.-9 61-7;3 *616.&**613 .l,-566. 6 -616. 9*-622.-&-*625.~-623 d *-** .. **--* -- -*-

581. 9 622.9 619.2 599.4 620.2 621.6 618.4 620.3

~

( ")

622.0 619.8 621.2 6?1.4 617.1 619.9 578.3 621.2 572.9 560./ 612.3 621.2 622.3 509.8 613.4 621:4 576.4 621.3 622.2 621.3 621.7 622.3

  • 619.~ 622.4 ****------- ..... -*-** ****** - ...

61~,.5

~D0.5 565.5 616.9 576.0 623.3 618.5 608.5 INDIVIDUAL RELATIVE FUlL ASSEMBLY POWERS <IN ASCENDING OROERJ:

  • 0,760 0.361 0.977 L089 LOSO 1-.081J 0.352 1.!39 l.*?.2'2 *1.240 1.050* *-

.,0.~00 1.241 0.000 0.801 O.CJOO 1.241 0.21~ l.10t, 1.233 1.208 0.000 'tj Ill rt 1.234 1.114 0.000 0.414 1.156 IJ.329 0.351 1.084 1.148 1.21~ 0.000 OQ rt 1,100 0.000 0.484 0.000 J.150 0.000 0.000 1.149 1.221 1.161 1,0{,7 rt) Ill 0.344 0.000 1.084 O.OOIJ 1.148 1,125 1.072 n l.,J ::r El

~VG. CORE INLET TFM~, FOk THIS CASE~ 549.6 0 H, ;:I rt) rt INCORE TC 8YPASS FLOW FRACTION= 0.1 \J1

~APIAL SYMMLTRY TILT F~LTOR6:

i*. Tl f2 T3 T4 15 T6 T7 T8 1*** 1.019 0.969 1.000 l.011 J,00~ 0.90~ J.071 1.019

4-22-83 UNIT 1

,) ..

r:r *----- -** .....,, ' DATE-JNCORE THERMOCOUPLE MnP 4/2Ull3 TIME- 14.52.56 TO 14.53~52 NORTII ANNA NO .1 POWER- 930. 7 Miff I~. CONTR(ll POSITIONS ROO GROUP SDA 228, STEPS GROUP, 2W. STEPS SD8 GROUP CM 2;!8, STEP!l BJ.:OlJP CP.P.

228. STEF'!l GROUP Cl',C 2W. STEPS

(;R(JllF' Cl',D n.3. STEPS F'L 2,lO, STEPS Ii,----------- --!* . *2 ----3* ----4-*-*** --5. *******-6 7 l!

B . 9 -* .... - 1IJ -11 .. -12 lf 14 1.5 l!

  • l! *

~70 DEG. CLOCKWISE l!:;11

~ ~;so.o * *

',' .! A Hl!

  • 37,135 * .. *

/

" 0,765

  • l! 561.ll *
  • 5911.1 *
  • 17.71!!'
  • 40.00 *
  • 0.358 *
  • 0.973 *

!f

  • 621..6 * ~ ~73.B
  • l!
  • lf 23.68 *

!f l! 1.157 I

  • CJ.:B'.i *
  • 569.2 * !f 612.9 * !f lf l!

.:,-. I

....

  • 19.10 l!------* " 62 .!JO* *l!** - * -- - - * ----*- - ----l! ***-*-***-* *
  • D.353 *
  • 1,()91) *

. ,, ,j;1 j:, l! lf l! I I l! !f

  • lf
J:

1*"

I *

~

617.5 67.36 1.UB6

~ 619.0

  • 68.82
  • l
  • 091 *
  • 621.7

~ 71.54

1. 150

~

.
~ 622.B*
  • 72.63 ;,;
  • 1.;!16 *
  • 613.1 *

~

62.94

  • 1..07:1 lf
  • ~67.2 *
  • 17 .114 lf

~ o. ;154 f H

C ')

(

  • 617.0 i. !f 62:!.5 *
  • 625.6 *
  • 623.1 lf
  • 509 .ll *
  • 66.86 *
  • 72, 35 I l! 75,43 I lf 72. 97 lf lf o.oo lf
  • 1.134 l! I 1.219 * .;,: 1.246" lf 1. ()45 * * (),000 i:

1( 1::1' l! 582.3

  • 613.8
  • lf I 6n.1 l! ~ 62l.7 *  ;,; !i76. 9
  • 1** G ****
  • 32,21
  • 63.613 * ~----*
  • 73.00 *
  • 7{;62 * -I  ;.: 26.79 *
  • 0.499
  • 1.101 *
  • I. 2~8 *
  • 0.0()(1
  • i: n.4B6 "'

j( 1:.:;

H H" lf

!f l!

l!

621.8 71.68 l!

l!

  • 622. 7 *
  • 72.53 lf .*

l!

I 619a3

  • 69.16
  • 71.68 *

~ 621~8 *

  • 622.1 *
  • 7 J
  • 96 ~
,; 622,6 *
  • n.1,:1 ,

lf lf 599.2 4S' .0:1 D.OOD 1.151

  • 11,0011 I 0.0011 0.11011 t, l 4fl *
  • p

.J J::i_,

f 620.4

!f l!

l! !f l! l!

  • 621.7 lf lf lf
  • 618. ft lf
  • '.1:

lf

  • D. 71!9 l!

.*.7,.i 1*' !f 70.31) *

  • 71.5:) :1:
  • 68.4] *

!f 0.000 lf

  • 1.n'.; * ~ 0. :~ 1~. ~
  • .l.
  • 62D.5 * " 62:*!.1 *
  • 619 ,8 * ... 6:~1.4 ~
  • 70,:i6 * " 71, 94 ;. * (,9,71 * ~* /1,;!7 :t

(

  • 1.10:-! l!
  • 1.2:u * ,* l. ill:! *  ;; 0.()()1) *

, 619. 7 ~: " f.22. S' " ~ (,)(,JI *  :/ ~1 8J

  • 2 +
  • 6'/ .60 * :1: ;:.~. 7::i :': ,- 6'.i.ll.S -" ,; :s l. l)'l ,;
  • 1.. :-!21. :( I J.164 ~ * , Lfl6S' + n. :i:, :i
  • ~j(,6.3 * *'!: i: 6:-'I.', * '* /,1/.,! :. +
t: 16. J."l ;i: ,* n .;*n ~ lf (,7.B *
  • 0.000 * ): t.:.,u i: * .l , l)IJI, ;;
  • td;,. I " i' (,I fl, fl X
  • (),[l()() * ..
608,8
  • 620.1 *

,.\ I 58.69

  • 69.93 *
  • 1,071 ;; 0,000 I
  • :,70.6 ~

I  :!!J, ~j( I

  • D.t,U
  • l.OOP-1 l.OOP-:? l.OOP-3 SYMMETRY CHECI(

INLET TE"P.!RTD)- 550,2 550.1 549.7 1.0:rn ~ 0.961l * .t ,OOB

  • AVG. TEMP.(RTO)- 581,4 58D.2  :;01. :1 * *
  • TEMP, RISF.!RTD>- 101,5 98;7 1DL 7* *  ;; ;; 1; ()17
  • 0. 90.J Jl.OW!PERCENT>- 99,9 99,6 99.5 * :I: *
    • * :ot:

SYSTE" PRESSURE= 2249,4 PSIA 1.010

  • 1.002
  • l.071 *
  • '1V6. OUTLET TEl'IP, FROM INCORE *T /(;* c 607; 1 -----

AVG. CORE INLF.T TEMP. FOR THIS CASE= 550.1 THERMAL POWErt

  • 2842.5 MWT MAIN COOLANr BORON CONCENTRATION=

... ' (

HIGHEST RELATIVE FUEi. ASSEMBLY POWER JS 1.246

  • AT LOCATION F- 9

SUMMARY

OF SYSTEM CHEC~S BASEO UPON INCORE THfRMOCOUPLES t"'

0 j.:*_l CORE SYMMETRY GREAiER THAN SPECIFIF.O LIMIT zG")

LOCArION B- 5 LESS rHAN LOWER LIMIT OF 0,424

(' .' *1 LOCATION E-14 LESS THAN l.OWER LJMil OF 0.394 ,......._ t-rj

'. J:*' - - - *** ** **--*-------******-** -***-* ---* -1:0CATION F- 9 F.XCEEOS-IJPPliR LIMIT-OF 1.160 n o LOCATION 6- 6 EXCEEPS UPPER LIMIT or 1.101 g ~

(*

LOCATION H- 8 LESS THAN LOWER l.IMIT OF 0.000 M'

  • f-3 LOCATION J- 2 I.ESB THAN LOWER l.IMIT OF D.000 t:*:i LOCATION J-10 EXCEEDS IJPPER LIMIT OF 1.167 '--' ( ")

.., LOCATION J-12 LESS THAN LOWER LIMIT OF 0.950

      • ----- ** ***-*-*--- -- *-*------LOCATION K-11 l.ESS-THAN-1:0WER UNIT OF --0;000
I

(( I *I LOCATION P- 8 LESS THAN LOWER LIMIT OF 0.000 l.OCArION C- 0 EXCEEDS UPPER LIMIT OF 1.050 LOCATION C-12 LESS THAN LOWER l.IMIT OF 0.424

,.. ,.,**. LOCATION D- 3 LESS THAN LOWER LIMIT OF 0.425 LOCATION E- 8 EXCEEOS UPPER LIMIT OF 1.151 LOCATION F-13 LESS THAN-LOWER l.IMIT-OF- 0,950 l"i NO REJECTEO THERMOCOUPLES

    • ,  : i DATE 4/22/83

~.

.. : NORTH ANNA UNIT 1" NET AUX GROSS BORIC :l~EACTOR:
GENERATION:CONGUMP-:GENERATION: ACIO :MAKE-IJP:

1 1 TION .. ;. FLOW .: FLOW I

.. / IIWH , MWH MWH GAL GAL "'

Ill >

M' I :~~~~-~--~~~~~---~-~~~~~--~--~~~~~---~-~~~~!-~-~~~~~-~

OQ M' ro n, n

.,r. 1506 : 800,61 49,4: 930,0: 0,0: 0,01 V,  ::r

" ----------------------------------------------------- o ro a

I

  • 1*1 Hi ::,

V, M'

_,. ... ~

-i I

.; 1 *1 1.. :

ATTACHMENT B Page 1 of 4 ADDITIONAL INFORMATION IN RESPONSE TO THE REQUIREMENTS OF NUREG-0737: II.F.2 ATTACHMENT 1 - Surry .Power Station 2 (a) See attached pages. These are examples of the printout display that is available to the Control Room Operator on demand.

(b) The range of all T/C printout locations available to the operator is 0° F to 700° F. The range of input and readout to the subcooling monitor is 0° F to 2300° F.

(c) There are no alarms associated with the incore thermocouple during normal operation. This system is used in conjunction with the flux monitoring system for power distribution. During upset conditions, the alarm functions are provided in conjunction with the Subcooling Monitors.

(d) Reference 3 addresses review of ICC instrumentation readout arrange-ments.

4 The post-TMI requirements for the upgrading of Reactor Operator training programs included specific training topics on the use of the primary and backup displays for the Incore Thermocouples. Since this initial training was completed, a retraining program was included in ensure proficiency in this area.

The emergency procedures were revised to provide for more closely monitoring the incore T/C's for the evaluation of core conditions.

These procedures will be upgraded further based on the WOG re commended guidelines presently under development. See Reference 3.

NOTE: The In-core Thermocouple System as well as other components of the Inadequate Core Cooling System may be upgraded to the current standards based on the results of Regulatory Guide 1.97 Analysis and Control Room Design Review If the results of Regulatory Guide 1.97 and the Control Room Design Review dictate an upgrade of the In-core Thermocouple System, then all training and procedures will be modified to reflect the upgraded instrumentation and capability.

ATTACHMENT B e Page 2 of 4 SHORT FORM T/C MAP 6

. SURRY UNIT 2. THERMOCOUPLE. AND FU£l ASSEHBL Y POWER ' POWER OUTPUT SUHHARY.

1042 DATE: 5/ 9/83 TINE START 10,40,56 UP TD 10,41,46 POWER 2456, 9 ffw I 799, 6 ffWE BORON CONCENTRATION /0'70 PPM

~ ',

REACTOR LOO? A VARIABLES: - '.-

fcIN TA~Gt--'f'A\l62. lDT1 TDT2 Ft6111 FLOV2-Ft-flOllf'll31-------------~------

545,4 574,9 574,3 61,3 61,3 99,0 100,0 99,2 .

,*:q REACTOR LOOP B VARIABLES:

I ,

iii/

T*IN

  • TAV&t-TIW62 .* TDT1
  • TDT2 FLOW1 f16112 . FLOIB

' I . 543,6 574,S 574,5 61,5 62,8 97,9 99,1. 99,7 .a-( f 1

'l 1

  • s' REACTOR LOOP C VARHiBLES 1:.1-1_ N_...,T...A'""Qij....1--1",TA""tJ""'G:-*_..,.TD""'1_l_l....,D1-2-F1....

_.,..r--1.... ,o....1i1-1-Fl o.-2,__..Fl..,.O'"'lt3------'----'-------------------------'---

'* 538,9 .572,2 572,5 61,3 62,0 99,8 98,7 99,5

\. f.:; SYSTEK PRESSURE = 2248,5 l

,.i AVERAGE 1ffCORE~..... PER l£1""1'1..............

ATI'"l:JRE--:-go-o....,,,,__---.- - - . -..-.. -. - . -..-.. --.-.-.,.- ... -.- - - - - - - - - - - -

. . ! INDIVIDUAL IHCORE T/C TEMPERATURES <IN ASt!ffDIHG ORDER>: * . *... *... . ,,.*

\ .. !c1 2

577,3 570,7 595,4 609,7 607,6 607,4 573,4 609,0 613,0 602~S 610,l

It-:_ _,s,H69,6 005.4 606,8 sso.2 602,7 600.2 613.9 o.o 610,5

  • o.o 613;6*

L, 61'3,5 611,S 601,2 570tt60~B7,2 575,0 610,0 611,0 611,9 611,9

.. ; I 601,1 609,7 564,4 600,8 611,9 607,0 0,0 603,8 612,0 609,,4 613,0 C ~* 1 3 o.o 0,0 613,1 582,B 606,0 6p.o* 596,0

  • I .

isl:..-'.--+iIHfl-IVIllU{d: RELATIVE A:IEL ASSEKBLY POWERS <IH ASCEHBIH6 BRIIER>:

. . lr: .

ji'i o,741 o,483 0.953 1.02s 1.114 1.189*0,475 1.138 1.214 1.120* 1.20s .:

0.422 1.130 1.069 o.733 0.914 1.1u 1.22a 0.000 1.20s 0.000 1.216 1,2311,142 0,936 0,392 1,115 O,S27 0,525 1,179 1,216 1.224 1,168.

  • ,. . .--o,-9~72,...1--,-...1B""0,. . .,0.,_,....42'4"'.....1'"'"",0""9"'"9-11-.2....0......4 +1-..1....77-0,"*oo-o-1-,""'09"'"7.....,1,_,2....1...-1-+1'-",2""03.-1.~1,e,95------------------

t: 0,000 0,000 1,196 O,S19 1,125 1,159 0,960

~ l2°l

,
./ AVG, CORE INLET TEHP, FOR THIS CASE= 361,9 Ir-----------,,-~-----,-,-----,--,.-,---_,......,...,.,,.,,,,.--,-,-,-.-=-,.,-~-,---,,---,----,.---,-----

r*! .' IHCORE TC BYPASS FLOW fRACTIOH = 0,050 . .'.,/. ., . "**;:..- ';°('{j<.

l

  • i?I . ' *' .* ,.;:
  • -~ 3 r:_- -... RADIAL SYfflfETRY TILT FACTORS: . . : , *, -: *t .' -.r.

,..1 11 12 13 H TS 16 T7 rs

\_..' r-si 0,986 1,~09 1,0110,9941,014 l,008,1,006 ~.972 txl REJECTED TC CHO,> - POSITION Vll~UE .

1~ _.  : K:O!ttt>-.- .-..""'6;5,N..,,1.--_,.-...- **- - - - - ; _ . , . . . - - - - , - . . - - - . _....., : ~ - .- - . , - - - - - - ~

0

, ,3'~* K09<21> .67,7 , . . : .*.*!..", ...

~ ; 'I = ff-11( 40) . 0*0 . :

iJ*:

_1.r- L-14(4S> *., 0,0 .

  • o-ac--tt\-,---'-_-.-_21)11,f~i-.:...~,-*-,--*_;,*-- .. --'---__;----.;... .. ____..;;.

ll4COJ\L l1n. . 4 l '.Jo.JI LE LHF - ouRr\l UNli L I1ATE- 5/ 9/83 TittE.1,42,56 lO 10,43,46 -POWER- 799,2 HIIE---*, - ATTACHMENT B -

" *

  • Page 3 of 4 COt; TF:OL ROD G~OUP SDA GF:OUP GROUP CBA GROUP CBB GROUP CBC GRO CBD PL .

POSITIONS 228, STEPS -- . 228, STEPS 228, STEPS 228, STEPS 228, STEPS 220, STEPS 227, STEPS l 2 3 4 5 6 7 B 9 10* 11 12 13 14 15 i

270 DEG, CLOCKWISE i

TOOOlA

  • t 576,4 t
  • LONG. FORM T / C MAP l214,58 l l 0,737 l - - - -i. -*** -*-*-*-***-*-*-*

T0002A

  • T0003A
      • t 570,7 t i208,92 t * *
  • t 594,9 t233,12 t
  • o.~83 * -* * *
  • t 0,951 t * . --------------- * -

T0027A T002SA

'** I ** ** *** - *

  • t 603,4 i l241,63 * **
  • i 587,0 t t225,20 t
    • --*- ------ i .

T0029A

  • 575,3
  • i T0030A
  • 610,0 S
  • i t 1,113 t
  • i S

t 0,527 i t

  • t i213,49 l S0,526S i248,23
  • Sl,180S i

S S

S *i T0004A TCiC*05A T0031A

  • T0032A T0006A T0007A
  • i 609,8
  • S
  • 607,8
  • 611,1
  • i 612,2
  • i 607,6
  • i 573,8 *
  • S t.247,95 i
  • t245,97 t249,26
  • i250,36 S i245,81 i i211,96 *
  • *
  • 1,026 * *
  • 1,175
  • 1,216 i
  • 1,226 S
  • 1,191 *
  • 0,476
  • T0008A T0009A T0010A T0011A TCiC*~3A t.U *.
  • 608,9
  • t 613,0 l * *
  • 602,7 l i 610,2 i i 612,0 i S l i247,12 * * *251,22
  • l S t240,91 * *248,35 t t250,15 * *
  • 1,138 * *----* 1,235 *--*--* *----- i*---- -- *i 1,128 i*---- i 1,206 i i Llt.S i i T0012A T0034A T0013A T0035A T0036A i
rU*569,4i600,7l
  • l *605,ll *609,7l l * * *
  • i564,4S t207,58 f.238,91 t 0.422 o.971
  • T0037A l

l . *243,29 l t247,B4 *

--**t-1.12s .. ----t 1.1ao 1--- - .------*--*-----

  • T0038A T0014A T0039A i t T0040A i

T0041A

    • t202,60 l
  • o,424 T0015A l
  • i 600,6 *
  • 612,0 i i
  • 605,7 i 607,0
  • t 0,0 *
  • 603,9 l i 580,S *
  • t238,83 i i250,15 i i i243,90 i245,22 i i 0,00 l f242,10
  • i218,64 l
  • T0016A
  • 1.099 **----i1*.2os-*------:-1*--~---* 1,064 1.11s*1-------*-o.ooo *- **

T0017A T0018A

  • 1.09s * -- -*

o,734 *----------

i tit t t 602,4 i i

  • i i
  • i . i 600,4
  • t 61~,1 t i i
  • i i240,59 *
  • i i t i
  • t i238;63 i t252,31 l t
  • i

-- -i----**- 0,973'1 ------*..- * * -. * ---...- . ir-.110

  • t1.23o*r--.---..--*-**-i---

Too19A T0020A T0021A T0022A Ul i i 0,0 i S 610,7** i t 0,0 i

  • i 613,8 l t i i i S 0,00 i '248,92 i i
  • 0,00 i i i

,---- ,-0,000, ***1;209

  • roo42A
  • o;-ooo
  • T0043A
  • 251,98 *

,-1,2i-s

  • T0044A T0045A tU i

.i t *t

  • i f

i 612,1 t t250,28 t t 609,2 f i247,37 f t

i i

t 613,4 l

  • *251,57 i t 0,0 *
  • S 0,00 i . .

,

  • 1----i i-i-.211--i **1,"202
  • i - - - i---i-1.1n-i----i*o*;1>00 *---*____,__ _____

T0046A

  • T0023A T0047A m .
  • o.o i o.oo i i
  • i . t t*
  • 613,7 *
  • 251,87 i
  • 613,4
  • i251,60
  • S l

,-0.000 *---1 *

  • i----t-t,-232 "* ------i-1,1n-1--**-- - - * - - - ~

T0048A T0024A T0049A T0050A t 583,1

  • t 611,7 t
  • 605,2 t
  • 612,3
  • t t

,------- ----** --~ ' -*. i221,32 *

  • * '249,88 * *243,42
  • o.s20 ----1-i.-iui--.-i1.120-.--,-i.1*611--i----------*-**-*----*---
  • 250,51 f l l roos1A roo25A Ix** . i l

i t

i595,9l601,4*

i234,06 i239,54 l i

f i

l i

- - - - - . - .-**---i*-o-;-160-.--0,-937*-i *----.------..--------- . -- * -**--*-

T0026A t 570,7 l

.i208,91 i i

  • -------i*-0,392-.---.----..---:-- --- *--*****- * *- * --**-

LOOP-1. LOOP-2 LOOP-3 SYHHETRY CHECK

- * - - - - - - - *-INLET*TElfP,(RTD>--****************************

545,-4--543,6--539,1'-----0,986 f 1,009 **************** S 1,-014 f------*-*--*----*-- --- ***--**---

AVG, TENP, (RTD)- 574,7 574,3 572,3 . i S i TEHP, RISE(RTD)- 61,6

  • 62,1 61,1 SSSSSt t 0,972 S 1,008 FLOWU'ERCENT>- 99,8 98,8 98,9 t . t t .,

---*-- - *-*---- SYSTEN.F'RESSURE =* 2248,0 PSIA------------- *0,9~4

  • 1,011 -- -* l 1,005 t ***-----------** -*** ... -*--*** *--

AVG, OUTLET TElfP, FRON IHCORE TIC= 600,6 AVG, CORE INLET TEHP, FOR THIS CASE= 361,B THERHAL POUER = 2461,2 HWT

--- ----- -- * * *- MIN COOLANT BORON CONCENTRATION =*-- *O;O PPt! -----

H!GHEST RELATIVE FUEL ASSEMBLY POWER IS 1,235 AT LOCATION F-05( 9)

ATTACHMENT B Page 4 of 4 2389-1 SURRY UNIT 1 T/C LOCATIONS (NEW) 2 3 4 5 6 7 8 9 10 11 12 13 14 15 I I I A

~ A

/

B

~ A D TC rr Bl' TD C

I/**,

D X ~ C . B '

E E [X D C>< C>< l'f I C>< A T T F B T C T B D TC J

G - [X [X

~ A T "

E D T H - E TA D T E T T TA TC T I

J - T D B CP TD TE c*

K T T T T L

1 .

C E TA T

.B E .

B T TA M . B - T T N

  • T D T E TD TA E p - T T R T C A- FLUX THIMBLE DETECTOR A
  • B- FLUX THIMBLE DETECTOR B (NEW THERMOCOUPLE LOCATION)

C- FLUX THIMBLE DETECTOR C D- FLUX THIMBLE DETECTOR D E- FLUX THIMBLE DETECTOR E CP- CALIBRATION FLUX THIMBLE !COMMON PATH)

T- THERMOCOUPLE r- =

) ( - INDICATES POSITION OF REMOVED T/C I s*.._

Figure 1-1. Distribution of Flux Thi111bles & Thermocouples

. ,.. - e COMMONWEALTH OF VIRGINIA)

)

CITY OF RICHMOND )

The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W*. R. Cartwright who is Manager-Nuclear Operations Support, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.

7L Acknowledged before me this / ;2- day of - - - - ~ - - - - - ' 19 }> .3 My Commission expires: e:i.. -:J-- ~ , 19 3~- .

Notary Public

-(.£EAL)

r. =
  • S/001
Retrieved from "https://kanterella.com/w/index.php?title=ML18139C340&oldid=2504796"