ML20237B586
| ML20237B586 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 12/08/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| 3941K, NUDOCS 8712160364 | |
| Download: ML20237B586 (10) | |
Text
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1 One First National Plaza, Chicago, Ilknois v
Address Reply to: Post Office Box 767 Chicago, Ilknois 60690 0767 December 8, 1987 Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Final Safety Analysis Report (FSAR) Amendment No. 49 NRC Docket Nos. 50-454, 50-455, 50-456 and 50-457 Reference (a): November 10, 1987 S.C. Hunsader letter to T.E. Murley
Dear Mr. Murley:
J Reference (a) provided you with Amendment #49 to the Byron /Braidwood FSAR.
The purpose of this letter is to provide you with corrections to minor errors that had not been identified during the final review of the Amendment, prior to its submittal. Attachment A provides an Errata, with the applicable pages listed. Also, attached are the applicable Byron /Braidwood FSAR pa'es, marked-up with the specific corrections that g
have been made. These will be incorporated in the next FSAR Amendment.
FSAR Appendix E.31, pages 17, 18 and 19, are being changed to restore the statements addressing the capability to trend specific Reactor Coolant System parameters and to address the availability of the spatially oriented core map. The intent of these changes is to state that these capabilities are available on lower level displays, but not on the primary (SPDS) display.
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Also, pages Q321.104-2, and Q321.104-3 were erroneously submitted in Amendment #49 as Byron /Braidwood common pages. The wording submitted in the Amendment applies to Byron Station only.
The attached marked-up pages reflect the descriptions for Byron and Braidwood and the appropriate separation into Byron and Braidwood pages.
In addition, a line that was inadvertently deleted during preparation of the Amendment is being restored to Byron page Q321.104-3.
8712160364 871208 PDR ADOCR 05000454 I
Sj
l T.E. Murley Decerabor 8,198*1 We regret any inconvenience that this may have caused you. Please direct any questions regarding this matter to this office.
Very truly yours, C.
S. C. Hunsader Nuclear Licensing Administrator
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Attachment i
cc: NRC Region III Office Byron Resident Inspector i
Braidwood Resident Inspector S. Sands (!GR)
L. Olshan (NRR)
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ATTACHMENT A BYRON /BRAIDWOOD PSAR AMENDMENT NO. 49 ggRATA Page #
p_hange E.31-17 Add:
"Also available on supporting lower level graphics is a trend of temperature margin to saturation."
E.31-18 Add:
"Also available on supporting lower level graphics are trends of liquid level inventory for reactor head and plenum".
E.31-19 Add:
"Also available on supporting lower level graphics are trends of core exit temperature and a spatially oriented core map indicating the temperature at each of the LET locations'!
Q321-104-2 Separate into Byron and Braidwood specific pages.
Q321-104-3 Separate into Byron and Braidwood specific pages.
Insert into Byron page Q321-104-3, second paragraph, after
" expertise":
... on shift, will only be to give technical direction for operation..."
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B/B-FSAR AMENDMENT The SMM inputs are routed from the sensors to the processing equipment via existing safety-grade cabling,' containment penetrations and signal isolation hardware.
E.31.3.2.4 Processing and Display Description The following subsections describe the processing and display for each of the ICC detection instruments.
E.31.3.2.4.1 Subcooled Margin Monitor The SMM functions performed by the process computer are as follows:
- a. Calculate the subcooled margin.
The saturation temperature is calculated from the reactor coolant loop pressure inputs (wide range).
The saturation pressure is calculated from the average of the ten hottest core exit thermocouple.
The temperature sub-cooled margin is the difference between the saturation temperature and the hottest temperature input noted above.
- b. Process all outputs for display.
The SMM routine processes the temperature and pressure inputs over the following ranges:
CET temperatures from 0
0 200 F to 2300 F, reactor coolant loop pressure from 0 to l
3000 psig.
The saturation temperature is calculated by l
the process computer from a saturation curve.
The following information is presented on the primary display:
- a. Temperature margin to saturation; and
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- b. Graphic display of pressure-temperature conditions.
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Additional information regarding the primary display, safety parameter display systems (SPDS) is included in Section E.17.
Backup displays are not provided for the SMM, however a procedure has been developed for operator use, utilizing the main control board displays for reactor coolant wide range pressure and the average of the ten hottest CET's to determine the subcooling margin.
E.31.3.2.4.2 Heated Junction Thermocouple
- Reactor Level The processing equipment for the HJTC performs the following functions:
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LUL 0 #L kna 4 kyua}ua. nargin h sahration.
E.31-17
B/B-FSAR AMENDMENT
- a. Determine if liquid inventory exists at the HJTC positions.
The heated and unheated thernocouples in the HJTC are connected in such a way that absolute and differential temperature signals are available.
This is shown in Figure E.31-10.
When water surrounds the thermocouple, their temperature and voltage output are approximately approximakhlh)zero.igureE.31-10 equal.
V on F is, therefore, In the absence of liquid, the thermocouple temperatures and output voltages become unequal, causing V to rise.
When V of the IA-C IA-C) individual HJTC ribes e)bove predetermined setpoint, liquid inventory does not exist at this HJTC position; b.
Process all inputs and calculated outputs for display;
- c. Provide an alarm output to the plant annunciator system when the HJTC detects the absence of liquid level;
- d. Provide control of heater power for proper HJTC output signal level.
Figure E.31-11 shows a single channel design which includes the heater power controller; and
- e. Provide an input to the process computer for percent liquid inventory level above the fuel alignment plate.
This output is an isolated signal.
The following information is presented on the primary display:
- a. Liquid level inventory above the fuel alignment plate
<[g (normal or low).
Adbitionalinformationregardingtheprimarydisplay, safety parameter display system (SPDS) is included in Section E.17.
The following information is presented on the backup HJTC display:
- a. Percent liquid inventory level above the fuel alignment plate for each reactor head and plenum' area derived f rom the eight discrete HJTC positions;
- b. Unheated junction temperature at eight positions; and
- c. Heated junction temperature at eight positions.
E.31.3.2.4.3 Core Exit Thermocouple System The processing equipment for the CETS will perform the following functions:
Also asidiJe o*, syeliy foun kwI yyhics aredr4 ep nguu texed inubey he rahr kal and l
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E.31-18
I B/B-FSAR AMENDMENT
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- a. Process all core exit thermocouple inputs.
Processing of 33 CET inputs will be performed by Channel A and 32 CET
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inputs by Channel B to the backup displays; s.-
- b. Calculate the average of the hottest reading CET's, for Train A and for Train B and provide outputs to the
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respective backup displays; and
- c. Provide data link outputs to the process' computer for all 65 thermocouple inputs.
These outputs are isolated signals.
These functions aOre intended to meet the design requirements of l
NUREG-0737, II.F.2, Attachment 1.
The primary display provides information on core exit temperature f-(the average of the ten highest CET temperatures).
dditional information regarding the prima'ry display and safety parameter display system (SPDS) can be found in Section E.17.
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The following information is available on the backup displays:
- a. Selectable temperatures of 65 core exit thermocouple.
Channel A display includes the thirty-three CET individual temperatures and the average of the ten hottest CET's (of l
33); and
- b. Channel B display includes the thirty-two CET individual temperatures and the average of the ten hottest CET's (of f
32).
Also aviola.ble. on syrfing low lwd rQics n $rds 0 9
core ud kpradura. and a. spa.fially orienkd core mg (inhutling h kpadm ad <ad of +k CET locadims.
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1 E.31-19 1
W2-FSAR AMENDMENT MOM I
EO's are assigned to radwaste operations, they are under the direct supervision of the Shift Radwaste Foreman.
The Radwaste Foremen involved with the initial operation of the VR system were
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trained by AECC through the use of lectures and/or video tape and participate in the initial testing of the VR system.
The Radwaste Foreman assignment is not routinely rotated among the shift foremen.
Individuals are assigned to the Radwaste Foreman position on a continuing basis to provide consistent overview and special expertise on shift in the operation o( the plant radwaste This staffing apptoach was devel'oped at Commonwealth systems.
Edison's four operating nuclear generating stations and has been demonstrated to be effective over the past several years in the operation of similar radwaste systems such as evaporators and demineralizers.
Rotation of EO job assignment helps develop the pool of personnel from which licensed operator candidates are chosen.
It also helps equalize the occupational exposure to operating personnel.
Day-to-day operating activities associated with radwaste are normally overseen by an Operating Engineer who deals with the operation of radwaste systems.
He is assisted by radwaste staff who track the' performance of radwaste systems and coordinates the modification and upgrade of radwaste systems when necessary.
Engineering personnel are also available on the Technical Staff
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to test and troubleshoot specific hardware problems.
Experience at the four other Commonwealth Edison operating nuclear stations has demonstrated the adequacy of this level of direction for 4
radwaste operations.
In summary, the general approach to staffing and training for radwaste system operation does not need to be modified for operation of the VR system.
Careful design means that operation of this equipment will be no more complex or hazardous than any nuclear power plant equipment.
As yith all radwaste equipment, special care will be taken in the superv.ision of VR system operation because successful, error-free operation is important.
The present approach to staffing and training is adequate to assure that all EO's can be properly qualified to operate the VR system safely under the direction of dedicated radwaste foremen.
Additionally, on February 7, 1985, Commonwealth Edison personnel j
met with members of the NRC staff to discuss their concerns regarding the initial operation of the incinerator portion of the volume reduction system at Byron Station.
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0321.104-2
Sp!>FSAR AMENDMENT j
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l As a result of that meeting, Commonwealth Edison had committed to y
retaining the services of a vendor representative to provide j
technical direction for at least the first six months of incinerator operation.
This commitment was made anticipating contaminated water would be processed by the VR system within several months of February 1985.
Operation of the VR system was subsequently delayed.
During this period Byron Station engineers have obtained considerable experience in the operation of the VR i
system.
Therefore, in lieu of a vendor representative, Byron j
Station engineers will provide technical direction during 9 il operation of the incinerator portion of the VR system for the
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first six months of processing cont'aminated waste.
The NRC found y
this acceptable as documented in an August 5, 1987 letter.
During the first six months the primary responsibility of the j
technical expertise of the incinerator.
At the end of the six
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j
(" months, Commonwealth Edison will decide if further technical 6
direction needs to be provided for this operation.
Commonwealth Edison will ensure that proper logs and data are kept and maintained so that an analysis can be made of the j
performance of personnel and equipment related to the incinerator operation.
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{cn sA;H wul only be h g>w. Mnial dimfim for opration 1
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Q321.104-3 j
J
FSAR AMENDMENT JE e
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EO's are assigned to radwaste operations, they are under the direct supervison of the Shift Radwaste Foreman.
The Radwaste l
Foremen involved with the initial operation of'the VR system are trained by AECC through the use of lectures and/or video tape and will participate in the initial testing of the VR system.
The Radwaste Foreman assignment is not routinely rota'ted among the shift foremen.
Individuals are assigned to the Radwaste Foreman position on a continuing basis to provide consistent overview and special expertise on shift in the operation of the plant radwaste systems.
This staffing approach was developed at Commonwealth Edison's four operating nuclear generating stations and has been demonstrated to be effective over the past several years in the operation of I
similar radwaste systems such as evaporators and demineralizers.
l Rotation of EO job assignment helps develop the pool of personnel from which licensed operator candidates are chosen.
It also helps equalize the occupational exposure to operating personnel.
Day-to-day operating activities associated with radwaste are normally overseen by an Operating Engineer who deals with the operation of radwaste systems.
He is assisted by radwaste staff who track the performance of radwaste systems and coor-I dinates the modification and upgrade of radwaste systems when necessary.
Engineering personnel are also available on the Technical Staff to test and troubleshoot specific hardware problems.
Experience at the four other Commonwealth Edison i
operating n~uclear stations has demonstrated the adequacy of this level of direction for radwaste operations.
In summary, the general approach to staffing and training for radwaste system operation does not need to be modified for operation of the VR system.
Careful design means that operation of this equipment will be no more complex or hazardous than any other nuclear power plant equipment.
As with all radwaste equipment, special care will be taken in the supervision l
of VR system operation because successful, error-free operation is important.
The present approach to staffing and training is adequate to assure that all EO's can be properly qualified to operate the VR system safely under the direction of dedicated I
radwaste foremen.
Additionally, on February 7, 1985, Commonwealth Edison personnel met with members of the NRC staff to discuss their concerns j
regarding the initial operation of the incinerator portion of the volume reduction system at Byron Station.
As a result of that meeting, Commonwealth Edison commits to retain the services of a vendor representative to provide technical direction for at least the first six months of incin-erator operation.
Also, Commonwealth Edison will provide l
qualified Byron test engineers during this period for technical direction during extended incinerator operation when the vendor representative is unable to provide continuous shift coverage.
321.104-2 j
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MgfpWO@
sps-FSAR AMENDMENT K pW O
During the subsequent six months, Commonwealth Edison has the discretion of providing only Byron test engineers for technical direction of incinerator operation.
During the first year, the primary responsibility of the technical expertise on shift will only be to give technical direction for operation of the incinerator.
At the end of one year, Commonwealth Edison will decide if further technical direction needs to be provided for this operation.
Commonwealth Edison will ensure that proper logs and ddtu are kept and maintained so that an analysis can be made of the performance of personnel and equipment related to the incinerator operation.
Additionally, after the first six months, Commonwealth Edison will meet at the Byron site with members of the NRC staff to review the lessons learned during the initial period of incinerator operation.
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O Q321.104-3