ML20248J422
| ML20248J422 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/30/1991 |
| From: | Eenigenburg E, Maxwell D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 91-425, NUDOCS 9107150391 | |
| Download: ML20248J422 (57) | |
Text
- - . - -_ _ _ _ -_ _ -_ _ _.
i , Commonwealth Edison
- Dresden Nuclear Power Station w , HR #1 Morris. Illinois f04$0 Telephone 815/942 2920 July 1, 1991 EDE LTR: #91-425 Director, Nuclear Reactot Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Conttal Desk
Subject:
Monthly Operating Data Report Dresden Nuclear Power Station Commonwealth Edison Coupany Dac ke LNna.,_30:010_50:21L _ and 50: 242 Gentlemen:
Enclosed is the Dresden_. Nuclear _Fnwer_Slatienlienthly_ Operating _ Summary Repott for June, 1991. This information is supplied to your office in accordance with the instructions set forth in Regulatory Guide 1.16.
Please note that the report contains information which had been previously submitted to your attention on an annual basis in accordance with 10 CFR $0.59.
Sincerely, E. D. Eenigenburg Station Manager Dresden Nuclear Power Station EDE:DMidwh Enclosure ec: U.S. NRC Region III Office Illinois Dept. of Nuclear Safety, State of Illinois U.S. NRC, Document Management Branch Nuclear Licensing Administrator Vice Pres. - BWR Operations General Manager - Nuclear Services T. S. Engr. (2)
NRC Senior Resident inspector Nuclear Quality Frograms - Dresden Nuclear Engineering Manager Comptro11er's Office Manager - Reliability Programs INPO Records Center File /N'RC Op. Data UdbO) 107150391 9t0630 ZR18/1463 PDR ADOCK 05000010 -
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- SUMMRY_0E_OrKRATINGEFERIENCE.
CMNGES.ESTS. AND_EKfERIMENTS FDLREQUIAIDRTEIDBJ,1(LAND _10_EDL50. 59 FDR DRESDEN_NUCiEAR_ ROWER _ STATION 00tt10NWMLTILEDISON_COMrAMT EOR _ JUNE._1221 UN1I DOCKET LICENSE 1 050-010 DPR-2 2 050-237 DPR-19 3 050-249 DPR-25 ZR18/1463/1 1
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. T IABLFJ f_.CONIENTS I 1.0 latroduction 2.0 Summary of_ Ooerating_hnerience 2.1 Unit 2 Monthly Operating Experience Summary for June,1991 2.2 Unit 3 Monthly Operating Experience Summary for June, 1991 3.0 Operniing_ Data _Slatialisa 3.1 Monthly Operating Data Report - Unit 2 3.2 Monthly Operating Data Report - Unit 3 3.3 Average Daily Power Level Data - Unit 2 3.4 Average Daily Power Level Data - Unit 3 3.5 Unit Shutdown and Power Reduction Data - Unit 2 3.6 Unit Shutdown and Power Reduction Data - Unit 3 3.7 Station Maximum Daily Load Dats 4.0 Vnique_Repor_ ling _Requirementa 4.1 Main Steam Relief and/or Safety Valve Operations - Unit 2 and Unit 3 4.2 Off-Site Dose Calculation Manua1 Changes 4.3 Major changes to the Radioactive Waste Treatment 4.4 Failed Fuel Element Indications 4.4.1 Unit 2 4.4.2 Unit 3 5.0 Pl an t_ o r_ Eracedure_ Change s . _Te als _Expe r imen t s . _and_ Sale ty._Rel a t e d Maintenance 5.1 Amendments to Facility License or Technical Specifications 5.1.1 Unit 2 5.1.2 Unit 3 5.2 Changes to Procedures Which are Described in the Final Safety Analysis Report (FSAR) (Units 2 and 3) 5.3 Significant Tests and Experiments Not Described in the FSAR (Units 2 and 3) 5.4 Safety Related Maintenance (Units 2 and 3) 5.5 Completed Safety Related Modifications 5.6 Temporary System Alterations Installed i
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ZR18/1463/2 l
e a i y 1.0 Introduction Dresden Nuclear Power Station is a three reactor generating facility owned and operated by the Conanonwealtb Edison Company of Chicago, Illinois. Dresden Station is located at the confluence of the Kankakee and Des Plaines Rivers, in Grundy County, near Morris, Illinois.
Dresden Unit 1 is a General Electric Boiling Water Reactor with a design net electrical output rating of 200 megawatts electrical (MWe). The unit is retired in place with all nuclear fuel removed from the reactor vessel. Therefore, no Unit 1 operating data is provided in this report.
Dresden Units 2 and 3 are General Electric Boiling Water Reactors with design net electrical output ratings of 794 MWe each.
Waste heat is rejected to a man-made cooling lake using the Kankakee River for make-up and the Illinois River f or blowdown.
The Architect-Engineer for Dresden Units 2 and 3 was Sargent and Lundy of Chicago, Illinois.
This report for June, 1991 was compiled by Donald C. Maxwell of the Dresden Technical Staff, telephone number (815)942-2920 extension 2489.
2R18/1463/3
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' ' 2.0 EUtttRLDEEEEAUH9_EXtERIENZ_E2A .llE,_1921 2.1 UNIT 2 MONTilLY OPEPATING EXPERIENCE StM1ARY 06-01-91 to 06-10-91 Unit 2 entered the month on-line and cperating in the RUN mode at 684 MWe, The unit operated until 0301 hours0.00348 days <br />0.0836 hours <br />4.976852e-4 weeks <br />1.145305e-4 months <br /> on 6-9-91, when an automatic main turbine trip occurred. The cause of the turbine trip was a thrust bearing wear detector malfunction. The turbine trip was followed by a reactor scram on high reactor pressure at 0302 hours0.0035 days <br />0.0839 hours <br />4.993386e-4 weeks <br />1.14911e-4 months <br />. The Reactor scram was caused by increasing pressure due to loss of feedwater heating.
06-11-91 to 06-30-91 After completion of the scram investigation and inmediate corrective actions, the Reactor was
--- made critical on 6-11-91 at 0020 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> and the Generator was synchronized to the system at 1108 hours0.0128 days <br />0.308 hours <br />0.00183 weeks <br />4.21594e-4 months <br /> of the same day. The unit operated through the end of the month with an availability of 92.21% and a capacity factor of 58.23 %.
On the af ternoon of 6-21-91, the Dresden Unit 2/3 discharge canal temperature recorder was approaching administrative limits for blowdown water temperature. To prevent a violation of Dresden Station's Environmental Protection Agency (EPA) permit requirements for blowdown temperature, the Dresden Cooling lake spillway gates were closed in order to isolate the hot lake water from the 1111nois River. Dresden's mode of operation was then switched at the lake flow regulating station from indirect open cycle to closed cycle operation with 50,000 gpm blowdown. A subsequent load drop was taken on both units for three main reasons: 1) To allow enough margin in condenser vacuum to run on two circulating water pumps per unit in order to limit flow input into the lake. 2) To allow enough margin in condenser vacuum to operate the units with the inticssed circulating water inlet temperature. 3) To limit the heat input into the lake in order to reduce future blowdown temperatures. On 6-22-91, lake temperatures -
were sufficiently reduced and indirect open cycle operation was resumed.
ZR18/1463/4
,' d SUtt1ARLOLOPERATING_ EXPERIENCE JOR_ J 7, 1 991 p
2.2 UNIT 3 MONTilLY OPERATING EXPERIENC '
SUMMARY
06-01-91 to 06-30-91 Unit 3 entered the month on-line, in the RUN mede and operating at 459 MWe. The unit operated the entire month in normal fuel.
depletion mode with an availability of 100.01 and a capacity factor of 54.20%.
On the afternoon of 6-21-91, the Dresden Unit 2/3 discharge canal temperature recorder was approaching administrative limits for blowdown water temperature. To prevent a violation of Dresden Station's EPA permit requirements for blowdown temperature, the Dresden Cooling Lake spillway gates were closed in order to isolate the hot lake water from the lilinois River.
Dresden's mode of operation was then switched at the lake flow regulating station irom indirect open cycle to closed cycle operation with 50,000 spm blowdown. A subsequent load drop was taken on both units for three main reasons: 1) To allcw enough margin in condenser vacuum to run on two circulating water pumps per unit in order to limit flow input into the lake. 2) To allow enough margin in condenser vacuum to operate the units with the increased circulating water inlet temperature. 3) To limit the heat input into the lake in order to reduce future blowdown temperatures. On 6-22-91, lake temperatures were sufficiently reduced and indirect open cycle operation was resumed.
ZR18/1463/5 I,
3.0 OPERATING DATA REPORT 3.1 OPERATING DATA REPORT - UNIT 'IMO DOCKET NO. 050-237 DATE _ July _l,lR91__
COMPLETED BY __ h _C J axwall__
TELEPHONE __{R11L2h2-222Q__
OPERATING STATUS
- 1. REPORTING PERIOD: Junes_1221
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 MAX DEPEND CAPACITY (MWe-Net) 772 DESIGN ELECTRICAL RATING (MWe-Net) 794
- 3. POWER LEVEL TO WilICil RESTRICTED (IF ANY) (MWe-Net): N/A
- 4. REASONS FOR RESTRICTIONS (IF ANY): N/A REPORTING PERIOD DATA This Month Yr-to-Date Cumulative
- 5. Il0URS IN PERIOD 720 4,343 185,231
- 6. TIME REACTOR CRITICAL (HOURS) 674.7 2,782.5 139,521.5
- 7. TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0
- 8. TIME GENERATOR ON-LINE (110URS) 663.9 2,594.3 133,567.1
- 9. TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0
- 10. TilERKAL ENERGY GENERATED (MWHt-GROSS) 1,125,866 5,123,266 276,727,409
- 11. ELECTRICAL ENERGY CENERATED(MWHe GROSS) 347,320 1,614,948 88,420,725
- 12. ELECTRICAL ENERGY GENERATED (MWHe-NET) 325,934 1,514,643 83,579,144
- 13. REACTOR SERVICE FACTOR (%) 93.7 64.1 75.3
- 14. REACTOR AVAILABILITY FACTOR (%) 93.7 64.1 75.3
- 15. GENERATOR SERUICE FACTOR (%) 92.2 59.7 72.1
- 16. GENERATOR A'!AILABILITY FACTOR (%) 92.2 59.7 72.1
- 17. CAPACITY FACTOR (USING MDC) (%) 58.6 45.2 58.4
- 18. CAPACITY FACTOR (USING DESIGN MWe) (%) 57.0 43.9 56.8
- 19. FORCED OUTAGE FACTOR (%) 7.8 22.1 10.9
- 20. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH)
NONE
- 21. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A ZR18/1463/6
3.0 OPERATING DATA REPORT 3.2 OPERATING DATA REPORT - UNIT TilREE DOCKET NO._0$0:249__ _ _ _
DATE _ July._lul221_
COMPLETED BY _ D.C,_ Maxwell._ _
TELEPil0NE _(8151 941:2920_
OPERATING STATUS
- 1. REPORTING PERIOD: J une ,_1291_
- 2. CURRENTLY AUT!!0RIZED POWER LEVEL (MWth): 2,527 MAX DEPEND CAPACITY (MWe-Net) 773 DESIGN ELECTRICAL RATING (MWe-Net) 794
- 3. POWER LEVEL TO WilICll RESTRICTED (IF ANY) (MWe-Net): N/A
- 4. REASONS FOR RESTRICTIONS (IF ANY): N/A REPORTING PERIOD DATA Thla Month Yr-to-Date Cumulative
- 5. IIOURS IN PERIOD 720 4,343 174,816
- 6. TIME REACTOR CRITICAL (110URS) 720.0 3,774.8 128.318.5
- 7. TIME REACTOR RESERVE SilUTDOWN (1100RS) 0.0 0.0 0.0
- 8. TIME CENERATOR ON-LINE (IIOURS) 720.0 3,708.1 123,343.6
- 9. TIME GENERATOR RESERVE SHUTDOWN (110URS) 0,0 0.0 0.0
- 10. TIIERMAL ENERGY GENERATED (MWilt-GROSS) 1,095,747 6,987,225 255,336,512
- 11. ELECTRICAL ENERGY GENERATED (MWile GROSS) 324,890 2,171,288 82,326,244
- 12. ELECTRICAL ENERGY GENERATED (MWile-NET) 304,122 2,051,772 78,026,191
- 13. REACTOR SERVICE FACTOR (%) 100.0 86.9 73.4
- 14. REACTOR AVAILABILITY FACTOR (%) 100.0 86.9 73.4
- 15. GENERATOR SERVICE FACTOR (%) 100.0 85.4 70.6
- 16. GENERATOR AVAILABILITY FACTOR (%) 100.0 85.4 70.6
- 17. CAPACITY FACTOR (USING MDC) (%) 54.6 61.1 57.7
- 18. CAPACITY FACTOR (USING DESIGN MWe) (%) 53.2 59.5 56.2
- 19. FORCED OUTAGE FACTOR (%) 0.0 0.0 11.4
- 20. SilUTDOWNS SCllEDULED OVER Tile NEXT 6 MONTilS (TYPE, DATE AND DURATION OF EACil)
- 1. Refuel Outage (D3R12) scheduled to begin September, 1991.
- 21. IF SilUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A ZR18/1463/7
4 S 3.3 AVEBAGILDAILLUNILEDEILLEVEL I
DOCKET NO._R$0 .23]
UNIT _IL DATE_J uly_l.a._1921-COMPLETED BY_D.J._tiar3 ell __
TELEP110NE_B15/941-1920__
MONTil JUNEt_L291 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (tNe-Ne t ) (MWe-Net) .
1 519 17 __ 3 19 2 5 10 18 MO 3 5 13 19 752 4 553 20 Z3B __
5 sit 7 21 63 L 6 570 _ _ _ _ .
22 3h4 7 624 23 303 i l
8 60f 24 _It23 9 3t tB 25 452
}{ -
10 0 26 313 11 195 27 3 14 12 490 28 479 13 420 29 450_ _
14 35] 30 331 ._
15 344 31 16 430 ZR18/1463/8
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3.4 AVERAGE _IWILL1WILEDWEILLEVEL DOCKET NO._Q50_249.-
UNIT _111 DATEJ ulyJ ._lRRl_
COMPLETED BY_Dn C._ Maxwell _.
TELEPil0NE_El5/912-22RO MONTl! AME, 1991 DAY AVERAGE DAILY POWER LEVEL DAY -- AVERAGE DAILY POWER LEVEL
-(MWe-Net) (MWe-Net) i- 1 khD. _ 17 416 l
2 435 18 3 Z5.___._
3 Ala- 19 - MS 4 3 15 20 4A1 5 4h8 21 3SD 6 451 22 356 7 407 23 297 8 4&3 -24 443 9 .437 25 323 l 10 4 14 26 279 L
l 11 470 27 319 12- 3 11 28 461- _
13' 4td 29 4A1 14 452. 30 623..
15 _ 417 31 16 - 3SL ZR18/1463/9
DOCiu:.1 NO. 050-237 UNIT NAME Dresden Unit II DATE July 1. 1991 _
3.5 liNIT SHUTDQFNS AND POWER REDUCTIONS COMPLETED BY D. C. Maxw_ ell TELEPHONE (815)942-2920 _
REPORT MONTH _ RIE. 1991 METHOD OF LICENSEE SYSTEM COMP 0pT CAUSE & CORRECTIVE I EVENT CODE" CODE ACTION TO NO. DATE TYPE DURATION REASON SHUTTING REPORT # PREVENT RECURRENCE (HOURS) DOWN REACTOR DET Automatic Turbine trip and 06-09-91 F 56.1 A 3 91-11/050237 IT 6 subsequent Reactor scram due to (56:07) turbine thrust bearing wear detector malfunction. Adjust-ments to the wear detector were performed and procedural impro-vements were implemented.
N/A N/A Load reduction taken to prevent 06-21-91 F 16.0 D N/A N/A 7 a violation of EPA permit requirements for blowdown temperature to the Illinois River.
3 4 1 2 Method: Exhibit G-Instructions for F: Fcrced Reason: Preparation of Data A-Equipment Failure (Explain) 1-Manual S: Scheduled 2-Manual Scram Entry Sheets for Licensee B-Maintenance or Test Event Report (LER) File C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-6ther (Explain) (NUREG-0161)
E-Operator Training & Licensee Examination 5-Load Reduction F-Administrative 5 Exhibit I - Same Source G-Operational Error ZR18/1463/10 H-Other (Explain)
DOCKET NO._Q10-2L9 UNIT NAME _Rrgsden_ _ Unit III UNIT SHUTDOWNS AND POWER REDUCTIONS DATE _.htly 1. 1991 -
3.6 COMPLETED BY _D. C. Maxwell TELEPHONE _{S15)942-2920 -
REPORT MONTH _J131 1991 LICENSEE SYSTEM CAUSE & CORRECTIVE
,, METHOD OF COMP 0 GENT EVENT CODE" CODE ACTION TO NO. DATE TYPE ~ DURATION REASON' SHUTTING REPORT # PREVENT RECURRENCE (HOURS) DOWN REACTOR N/A N/A Load reduction taken to prevent 2 06-21-91 F 16.0 D N/A N/A a violation of EPA permit requirements for blowdown temperature to the Illinois River.
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Method: Exhibit G-Instructions for F: Forced Reason: Preparation of Data A-Equipment Failure (Explain) 1-Manual S: Scheduled 2-Manual Scram Entry Sheets for Licensee B-Maintenance or Test Event Report (LER) File C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Other (Explain) (NUREG-0161)
E-Operator Training & Licensee Examination 5-Load Reduction F-Administrative 5 Exhibit I - Same Source G-Operational Error ZR18/1463/11 H-Other (Explain)
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. 3.7 COMMONWEALTH EDISON COMPANY - DRESDEN NUCLFAR POWER STATION MAXIMUM DAILY ELECTRICAL LOAD FORM FOR THE MONTH OF JUNE, 1991 ,
Day Hour Ending kWe 1 1300 1,173,200 2 2100 1.116,000 3 1300 1,126,400 4 1700 1,237,400 5 1800 1,247,400 6 1600 -1,248,600 7 2400 1,284,700 8 0700 1,293,600 9 0100 840.100 10 0100 513,300 11' 2000 1,014,000 12 1500 1,036,000 13 0800 1,015,400
~14 0700 901,300 15 2000 875,800 16 1700 1,068,300 17 2300 1,213,300 18 2400 1,281,300 19 1200 1,294,200 20 0900 1,291.400 21 0100 1,227,100 22 2200 779,800
-23 2200 729,600 24- 2400 1,074,500 25 0100 1,003,100 26 0100 709,400 27 1900 898,400 28 1300 1,097,500 -
29 0600 1.068,900
-30 0300 864,900 ZR18/1463/12
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s_._ . _ _ _ . _ - . _ __ _ ____ _ . _ . . __
4.0 UNIQUE REPORTING REQUIREMENTS
.4.1 MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period, June, 1991, are sununarized in the foll
- wing table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.
Valves No. and Type Plant Description Unit Date Attuates) oLAttuatiens CondiLions _oLEvento 2 No Unit 2 Main Steam. Relief and/or Safety Valve actuations occurred during this reporting period.
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3 No Unit 3 Main Steam Relief and/or Safety Valve actuations occurred during this reporting period.
4.2' 0FF-SITE DOSE CALCULATION MANUAL (ODCM) Cl!ANGES A summary of changes to the ODCM are provided on the following pages.
s ZR18/1463/13 i
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lc CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL Changes to the Offsite Dose Calculation Manual (00CH) are reportable to the Nuclear Regulatory Commission (NRC) in accordance with station Technical Specifications. This document contains the models for the public dose assessment from gaseous effluents, liquid discharges, and direct radiation.
The NRC, per Generic Letter 89-01, requested that the information found in the station Radiological Effluent Technical Specifications to be transferred to the 00CH and Process Control Program (PCP), as applicable. The major changes to the ODCH complied with this request. The remaining minor changes were editorial, outstanding from the previous distribution, Revision 0, dated March, 1989.
This revision does not reduce the accuracy and reliability of dose calculations or set point determination methodology.
Any changes to the OOCH computer program required by this document are in the process of being implemented now and should be fully available by July 8, 1991.
MAJOR CHANGES The generic manual both introduces and references the Radiological Effluent Technical Specifications contained in the site annexes, in Chapter 12, now titled the " Radiological Effluent Techu1 cal Standards (RETS)".
" Operability Requirements" in the RETS are equivalent to Limiting Conditions for Operations in the station Technical Specifications.
The generic manual is common for six sites, therefore the reporting requirement for " Changes to the 00CH" deviates slightly from the recommendation given in the Generic Letter. An effective date for generic manual implementation is to specified in the station Onsite Review. As in the past, the official transmittal to the NRC is made through the stations' Monthly Operating Report within 90 days of the effective date.
HINOR OIANGES The remaining minor changes are editorial. Below is the abbreviated version of an itemized list of changes available in Emergency Preparedness in at the Corporate Office:
- Revised titles for the Corporate Offie e Department and Positions
- Prepared a stand alone section for the EPA's Clean Air Act (if and when enacted)
- Deleted references to Commonwealth Edison (or CECO)
- Added text regarding the Hilmington Public Hater Supply nearby Braidwood Station
- Corrected parameter symbols, values and units.
ZODCH/81/1
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CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (con't)
SITE SPECIFIC ANNEX CHANGES Dresden Station (Chapter 10, I? 12 and Appendix F)
Chapter 10 - Revised the original sentence by Section 10.1.4.1 p 10-9 inserting "The recorder, controls, indicator and trip units, alarms, and annunciators are located on the 902(3)-2, 902(3)-3, and 902(3)-10 panels in the main control room."
Section 10.2.2 p 10-14 Added sentence to read " Liquid effluents are not released from Unit I storage tanks directly to the environment but are made through Units 2/3 Radwaste System."
Section 10.2.5 p 10-15 Added sentence to read "The discharge valve is locked closed at all times except during the discharge. All other lines which tie in with the discharge line are locked closed. The high and low flow..."
Other minor editorial changes Chapter 11 -
Table 11-1 p 11-2 Deleted gamma isotopic analysis on quarterly air sample particulate composites.
Table 11-1 p 11-5 Revised distance and direction for the ground /well water monitoring location 0-23, Thorsen Well, frcm 2.0 mi N (3.2 km A) to 0.7 mi S (1.i km J).
Table 11-1 p 11-6 Revised milk monitoring location, 0-26, from Trotter to Halpin's Dairy.
Other minor editorial changes Chapter 12 - New RETS insert *
' Insert incorporates the removal of 3.25 limit on surveillance interval extensions per NRC General Letter 89-14 200CH/81/4
- 4 e CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL-(con't)
SITE SPEC'JIC ANNEX CHANGES Dresden Station (cont'd)
Appendix F -
Table F-3 p F-4 Revised the Nearest Resident distance from 1000 m-to 966 m.
Table F-4 p F-5 jded the sentence as Footnote b,
" Mixed mode values are not needed for Dresden I since there is no mixed mode release point."
Table F-8 p F-40 Revised the distance, Rk_, from 1000 m to 966 m.
Other minor editorial changes l
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Z00CH/81/5
. . . .x
SUMMARY
OF CHANGES ,
SUBJECT PAGE' ACTION DESCRIPTION Signature Page N/A. Revision Revsed Emergency Preparedness Supervsor to Director.
ODCM Revision Index i- Revson Updated to inciede a new index designations on pp i-xii-'
Special Notes li Deletion Deleted page. Page number is used for a new index desgnations.
Revision Designation Deletion The new index desiyiniions are identried on pp i-xii.
Organizationof this Manual Deletion Refer to Section 1.4, p 1-6.
10CFR20 Hevsson Refer to Section 1.2.1, p 1-4.
i Notation for Powers of 10 Revsion Transferred paragraph to a note in Section 4.2.1.1, p 4-12.
Table of Contents iii Deletion - Deleted page. Page number is used for a new index desgnata>ns.
. iv . Revsson Page number is used for a new index designations, refer to revsed pages TOC for Table of Contents.
Rettled the Table of Corsents to Summary of Topecs.
Revsed 9.0 caption from
- References *to
- Reserved for the Clean Air Act*.
- References
- is a suject-ttled chapter. Revised Part 11, to include Chapter 12.
Notes on Table of Contents v Deletion Deleted page. Corsolidated a listing of contents, appendees, tables, and figures in front !
of the genenc manual i Detailed Listing of Contents v Deletion Deleted page.'
Listing of References v- Deletion Deleted page. The references are contained in a subject-titled chapter.
List of Acronyms viii Addition Page number is used for a new index des.ysaiions, refer to revsed p TOC-17 to 20.
Inserted Nucieer Services Emergency Preparedness and Operability Requirements on p TOC-19. ,
Revision - Revised the "S* in RETS from Specircations to Standards on p TOC-19.
ix Addition Inserted Unit Review Group on p TOC-20. ,
S
Chapter 1 -
Table of Contents 1-1 . Revision Revised Section heading 1.2.4. from p 1-5 to 1-Sa. [.
1-E Deletion Deleted d CECc MM-' 9tMW.
Section 1.0 '1-2 Deletbn Deleted Ceco four times. -
Addition Inserted the acronym, (ODCM).
1-3 Revision Revised Tecinial Specifications to Radiological Effluent Technscal Standards.
Deletion Deleted CECO. ;
Section 1.1.1 1-3 Deletion Deleted in.'
Section 1.2.1 1-4 Revision incorporated text from p li.
Sectbn 1.2.2 1-5 Revision The bold text was inserted and the barred text was deleted.
The NRC requires that the statiorm' Radiological Effluent Technical Specificatione, formally a subset of the Technical Spectrications, shall be incorporated into the.ODCM (see Reference 80). A Radiological Effluent Technical Standards (RETS) section for each station is found in the site specific annexes in Chapter 12.
5 2 ~~M*: P-"~j^^' E'" M T~^^-~~' 9^^^9?h
'RS),
rM ^' M T&-' S,^^^'^~M, rh !W-' Mr
-ei The RETS contain vadous radiological limits mandated by the Code of Federal Regulations and are made conditions of the stations' operating license. Typical offsite dose and concentration limits of the RETS are summanzed in Tables 1-1 through 1-3.
Section 1.2.3 1-5 Deletion The bold text was inserted and the barred text was deleted.
Compliance with the dose limits in the RETS is determined pnmarily by calculations based on measurements or radioactuity in stations effluents.
The RE33 Technical Specifications requred each station to have a documeilt called the Offsite Dose Calculation Manual (ODCM) to provide the methodology ,
and parameters for these t ah dation. h?._W h r".^d W ^" ~~M te !M ."'O '^ r^t ; ^^d E -&M W !M "& M ~^^^'d_-^^ rt j p'^^Mr^ rp^^'M h t TM-' 9p-^^~%. Changes in the manual are subgect to a prescribed internal review process and then sutested distributed to the NRC.
Section 1.2.4 1-5 Revision The text from p 1-5 is unchanged and is found on p 1-Sa.
Section 1.3 1-6 Deletion Deleted Ceco
Chapter 1 Cort'd
~-
Section 1.4 1-6 Revision Inserted the acronym, ODCM, for Offste Dose Cak:ulation Manual Deletion Deleted CECO Addition nserted Chapter 12 and.
Deletion Deleted a C^--^~d5 Eer C^--~~j.
Deletion - Deleted CW e rh :tr *^' M d tM ph pod = d L% ~_. '
Add 6;n - Inserted Chapter 12 is the stations
- RETS.
Table 1-5 1-9 Revson Revsed Techncal Specircations to RETS.
Figure 1-2 1-11 De'etion Deleted d CECe P '^r 9tMb r.
i-12 Revson Revsed Tech Specs to RETS.
Deletion Deleted 2 CECe 9?rr 9??Wr.
1-13 Revsson Revised Tecincal Spectications to RETS.
Deletion Deleted N.
l i
i l
r 1
,i.
~- -
I p Chapter 2 Table of Contents . 2-1 Revneon Fhmsed Section heading 2.2.2 from p 24 to 2-8c. '
Reveson Revised Section heading 222.1 from p 2-8 to 2-8c. L ,
4' Revisson Revised Sechon heading 2.2.2.5 from p 2-10 to 2-11.
- Revision Revised Section heading 2.3 from p 2-10 to 2-12. -
q List of Tables 2-li Deletion The barred test was deleted and the bold text was inserted . j Table heading 2-2.
! Standesd R=rtaingral Efnuert Techncal Standards S;: ~ ^ x 5 " 5? '"" M " 5? '"" ;
! - Section 2.1.2 2G Reviseon inserted text from Section 22, p 24 and 2-7. l l Revisson Inserted the acronym, NRC, for Nucisar Regulatory Commessson on p 24.
l Section 2.121 2-3 Revision The tend from p 2-3 is unchanged ano is found on p 2-4. [
l Section 2.1.2.2 2-4 Revieson Revned plant Techncal Spec 5icahon to erasen RETS.
Revesson The text from p 2-4 is unchanged and is found on p 2-4a. l l 2-5 Revisson - The tend from p 2-5 is unchanged and is found on p 2-4a.
Section 2.1.4 24 Rownion .- The text from p 24 is unchanged and is found on p 2-5. ,
Revesson ' The bold text was inserted and the bemed text was deleted.
However, leur five Ceco statsons (Braidwood, Dresden, LaSage, Quad C4hes, and Zion) have afiar'=1 reqtaroments !
- related to 40CFR141in their TC "?;-_~
_RETS. ,
Section 2.2 2-6 Delsbon Transiemed text from Section 2.2 p 24 and 2-7 to Section 2.1.2, p 2-3. : i 2-7 Revision The bold tesa was inserted and the barred text was deleted on p 2-6. i j The Radmiogeal Elnuent Technical Specticahons (RE3S) were forsnerly lones a es* mar of the Technmal Spec 5icahons. {
They implement provesons of the Cods; of FedeialRegidanons amed at limting offsee rartarian rinam The NRC paidahos standerd Radiological Efnuent Technical SpecNications RE3S f for PWRs (Reference 2) and standan844ETS-for BWRs (Reference 3)..
These documents have undergone frequest menor remoions to reRect ,
i changes s'i plant design and evoMng reguistory concems.
I Addition The bold text was inserted and the barred text was deleted.
l This section has been removed from the Technical Specincations ';'
and pieced in the oDCRA as Radiological Efnuent Technical Standards i (RETS). Refer to the NRC Generic Laser 8941 (Reference 80). The acronym, .
. "RETS*, remains dos to he high recognhlon. The purpose for retaining ,
- RETS* le to esse the tranetton of the Standard's ;i::-_:= to the ODCRA i and reduce the IIkellhood for inadvesient .e--:-:T;iA ,
Chapter 2 Cont'd Section 2.2.1 2-7 Revision The bold text was inserted and the barred text was deleted.
The RETS of each CECO station are similar, but are not identical, to one of the standard verscos 81adiological Effluent Technical Specifications.
Revsson Revsed RETS to Radiological Efiluent Technca! Specircations.
Revision Inserted the acronym, ODCM, for Offste Dose Calculation Manual 2-8 2-8 Addition The bold text was inserted.
The major categories of items in RETS are the following:
- Definitions A glossary of terms found in but are not limited to the ODCM.
- Instrumentation This section states the Operablitty Requirements (OR) for Instrumentation performance as well as the associated Survelliance Requ'.tenents. These conservatNe alarm / trip setpoints ensure the regulatory compilance for both liquid and gaseous effluents. Survelliance Requirements are listed to ensure ors are met through testing, calibration, inspection and calculation. Also !ncluded for such categories are the Esses for interpreting the requirements.
The Operability Requirement or an OR is the ODCM equivalent of a Umiting Condition for Operation as defined ha both the Standard Radiological Effluent Technical Specifications and the stationa' Technical Specifications.
- Uquid Eff!uerf.s This section addresses the Ilmits, special reports and liquid waste treatment systems required to substantiate the dose due to liquid radioactMty concentrations to unrestricted areas. Survelliance Requirements and Bases exist for liqu'd effluents.
__- 4
o Gaseous Effluents Chapter 2 Cont *d This section addresses tre IlmMs, special re. pats, gaseous radwaste srd ventilation exhaust treatment systems necessary for adequate docurlentation of -
the instantmeme offsne radiation dose rates and dcses of a member of the pubilc. Surveillance Requirements and Bases exist for gaseous effluents.
Addiion
- Environmental Monttoring Secten 221 24 cont.
This section delineates the environmental monitodng program 1.1volv6g sample collecbon and measurements to verify that the radiation levels released are minimal. This section describes a land use census ara par *Jcipation in an ir.terleboratory comparison program. Surveillance Requirement &W Bases exist for environmental monitoring.
- Recordkeeping saw Reportbg This section serves as an administrative guide instnuted to maintain an appropriate recoedtracking system. The management of procedures, record retention, review /audst and reporting are discussed.
Revison Remed RETS to Radiological Emuert Teda scal Spec (cations on p 2-8c.
Section 222 2-8 Deleton Deleied CECO on p 2-Sc.
Revision Revised RETS to Radological Emuent Tectncal Specicatons on p 2-8c.
Section ? ? ? 1 2-8 Revzsaon The text from p 2-9 is unchanged and is found on p 2-8c.
Revison Revised RETS to Radiological Emuent Techncal Specicata 2-9 Revision inserted the acronym, PCP.
Revision Revcod RETS to Radologeal Emuent Ted = scal Specicatons.
I Section ? ? ? ? 2-9 * *
- Secton ? ? ? 3 2-10 Revnson Revision Revised PE" d CCCo to the stations' Technical SpecN1 cations. .
Revision The texf. from p 2-10 is found on p 2-11.
Section ? ? ? 5 2-10 Rt.visson Revised RETS to Radologcal Emuert Techncal Specicarons on page 2-11.
Revisson Inserted the acronym, PCP, for Process Control Program.
Section 2.3 2-11 Revision Revised RETS to Radoiogcal Emuent TechncalSpecfcations on pary 2-12 2-12 Revision Revised the definston of ODCM to that rewnu.eaded in the Generc Letter 89-01.
Section 23 Revision Insened the acronym, NRC, for Nuclear Regulatory Cor tr 1:ssaart Secton 2.5.1 2-13 2-16.17 Revision Revised RETS sectens references.
Table 2-2
5 I
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llI
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st
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=
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IJ 1111 11Iii u a2 nx :
hh E;
Chapter 4 List of Tables 4-s Deletion Deleted b; CECe n Table heading 4-;L 4-1 Deletion Deleted Ceco. .' .
Revison Revised Radologcal Emuert Ted .c4 Specfcations to RETS.
Section 4.1.1 4-1 Revison Revised *kept in rrund" to *kept in wup. -
Section 4.1.3 4-2 Deletion Deleted 6 Revuon The text from p 4-2 is unchanged and is found on p 4-3.
Revision Revised Radological Emuent Techncal Specreations to RETS on page 4-3.
Section 4.1.4 4-5 Debtion Deleted Ceco Section 4.1.5 4-5 Revsson Revoed Table D-5 to D-9.
4-6 Deletion Deleted Ceco Section 4.2 4-9 Revsson Revsed Radologeal Emuert Ted s k.M Specications to RETS Secton 421 4-11 Reveson Revsed the Mammum Beta Energy Range from 0.44 to 0.34 ft.
Section 421 4-12 Revsson Revsed Techncal Specfcations to RETS.
Section 4.2.1.1 4-12 Revison Revsed the gamma abbreviation to the symbol in Equanon 4-3.
Revsson Transferred text, *Notabons for Powers of 10", from p il Revson The text from p 4-12 is t 4e =gM and is found on p 4-12a.
4-14 Revson Revsed " sections
- to " sector".
Section 4.2.1.2 4-14 Revson Revised the beta abbreviatior 'o the symbo, u Equaron 4-4.
4-15 Revson * * * * * *
- 4-16 Revson Revsed Table D-10 to D-14.
Addtion Inserted the before gamr".a dose factor, the shape Section 4.3 441 Revisaon Revsed Radsologcal EfNent Ted. .c4 Specicauons to RETS.
Deletion Deleted Ceco 442 Revision The bold text was inserted and the barred text was celeted.
The radioact. 'y concentration in water C*, [pC&TJ is the ps<xkc:
i d t*= %: obtelned by dividing the radioactivity released [pCI] by the volume of water (L] in which the release is diluted (e.g., the now in L/hr multipiled by the time period of concern in hours). The result is multipiled by the following:
4-33 Deletion Delete the barred text
" r~M M +;-Wre{pq.
"" d:~" d m %n ** r&rc ? ^1 M {c g . T= r *c h LW
~5W 5; = the p~M d mm M '"m).
4-33 Deleton Deleted Ceco
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Chapter 6 .
Secton 6.0 6-1 Deletion Deisted RETS Section 6.2.1 6-2 Rwison Revised RETS to Radokgcal Effluert Techncal Speedicabons.
Secten 622 63 Rens:en * * * * * *
- Secton 6.2.3 64 Revision Delebon The barred text was deleted.
~. ,.r,. ,___ a n. ,,n. - - c,.-....,-..a.n..--.
.~ - __ - , .
,--_,__r-,,.,,-- , . . , - - , -, -p
--_--.---~,,G r , n
._-_ a - ._ _,
J - 4 L u.,_._.__...,,,,.,,,,a.._.--..
_ o . .
.,, __ __ _- s,_.
v...,..-...__.-.-...
c._~..__. ,, . . - , . . .-. ,-~. .-, -~ . . - . - _ .,__
.a . _~r-.a_._,,....~__.a..__._..._. _
__J . > _a _-1 - ,
__-_-,r-wg.rw u -
- u. ,r- wm - w mm v v s._
-w.. .:m ew _-=rm 4
Secton 6.3 64 Additon Inserted Genene Letter 89-01 dernbon for the Process Cortrol Progrant Revisen Revised IETS to Radolor.ai Effluent Techncal SN Secton 6.4 6-5 Revison e-w
Chapter 7 -
7-iii Addaion Inserted Regulatory Guide 4.8 for in List d Figures headsrg 7-1.
List of Figures Revsiort Revised *ot* to "for*.
- 7-1 Revsson Revised RETS to Radiological Effluent Techncal Specicarons.
Section 7.0 Deletion The barred text was deleted.
S& r~;~*: ~e r~9M '~ c2ch CECe d?6_ % f%
c~*M ^' d?M Th^' SpMrM should be consuted for the appopiiate datak-Deletion The stations
- Tm.i. .c i Specications references were deieted.
Addition The bold test was added.
Sections 12.6 of each statiorfs RETS should be consuted for the appropnate details.
7-2 Deletion Ds.4eted CECO.
Sec' ion 7.1 Revision Revised Process Cortrol Prograrn to PCP.
Revsson Revised Techncal Specreations to RETS.
Section 7.2 7-3 Deletion Deleted CECO four tmes.
Revson Revsed Techncal Speercatsons to RETS.
Revsson Revsed Section 4.3 to 5.3.
7-4 Revsson Revsed Techncal Specreations to RETS.
Deletion Deleted Ceco Section 7.3 74 Deletion 7-5 Deletion Revsed Techncal Specicabons to RETS. l Revsson 7-7 Deletion Deleted CECO.
Section 7.4.2.2 Revsion Revsed Techncal Specfcations to RETS.
7-8 Deletion Deleted CECO 7-9 Deletion Stations
- Techncat Specreations references wwe deleted.
Table 7-1 Addtion Condensed Table 7-1 onto single page, p 7-10 is irtentiona9y 7-10 left blank.
e Chapter 8 Revson Revsed Techncar Sennces Emergency Plannng to Section 8.0 8-1 Nuclear Sennees Emergency PrepacG & -
Revson Revsed CECO orgarazaton plan from Jaruary to December,1989.
Revson Revsed Process Cortrol Program to PCP.
Secton 8.1 8-2 8-2 Revson irsened the acronym, NSEP for Ted.. cal Sennces E>Tepay. Planrung Secton 82 to NSEP.
Secton 8.3 8-3 Revson Secton 8.4 8-3 Revsson Revson laserted tt,e acroryn. ODCM, for O*fste Dose Cah deinn Marual Revson Revsed Computer Sennces Dmson to trformation Sennces.
Chapter 9 Revsson The references crxtained in Chapter 9 were trans*med 9-1 to a subject ttled chapter.
9-1 Addton inserted Reserved for Clean Air Act.
References R-1 Revsion Subsct ttled chapter. References.
Addton Added Refererce 80, Genenc Lener 8941.
l R-8 Add: ton Added Reference 81.
- Assessment of the impact of Liqud Radcactue Emuerts
- rom Bradwood Station on Proposed Ptblic Water triakes at Wiirnington, i5nos*, J.C. Golden.
NSEP January 1990.
i f
i Appendix A ,
A-i Deletion Deleted Types in Release Poirt Classicauons in SecW headrig A.1.1 - - .-
Revison Revsed Section heading A2.5 from p A-43 to A-44.
1 -
- A-i ' Deletion Deleted CECe and inserted Station in Secuon heading A42. [
A-iii Deletion Deleted '~ CECe MMr ???M in Table heading A-1 Deletion Deleted .'"~*-d W cec 9_Wr 9'?M in Tabie headrig A-2.
Section A.1.1 A-1 Deletion Deleted CECe Deletion Deleted Types in Releaso Point Class (cations in Secton headrxj A1.1. ;
A-2 Deletion Deleted CECe Section A.12.1 A-2 Deletion The bered text was deleted.
% Ted 9e?Mr M e9 CECc ??M contairs a somewhat i smiar provssort Fe -r -~ m , er !N Mm ege?m:
Addition The bold text was added. }
Sections 12.4 of each station's RETS contain a somewhat samilar provsiort AG Deletion The stations
- Techncal Specifcations references were deleted. lt A4 Deletion The barred text was deleted.
H TW" W~% M -H CECe ??P contaan a somewhat f similar provssort Fe - ^~?me, r~'!N Wq epR?W: ;
i Addtion The bold text was added.
i Sections 12.4 of each station's RETS corsain a somewhat samaar provsaort
- Deletion The stations
- Techncal Specfcanons references were deleted.
Revsson Rev'sed Techncal Specticat. ions to RETS. i Secton A.1.22 A-5 Deleuon The barred text was deleted. .
uma em ,w a
- a. re c^ ~~" cortain a somewhat similar provsaort Fe -r r-~"mr, r-!N ?% rWeth: I Addtion The bold text was added. ;
Sections 12.4 of each station's RETS cortain a somewhat similar provsiort ,
Deletion The stations
- Ted. zd SpecFcations references were deleted.
Revsson The text from p A4 is unchanged and is found on p A-5.
A-6 Revsson Revsed Secton 4.1.5 to 4.1.6 in the dersnaion for (X/Q), ;
! A-7 Deletion The barred text was deleted.
W T&M 9g3"?% M -9 CECe ??% cortain a somewhat similar !
provsort Fr -~ :-~?me, := !N % ege?h: !
Addition The bold text was added. !
Sections 12.4 of each station's RETS cortain a somewhat smlar prinssort l i i
4 Appendix A Cort'd.
Section A.12.2 A-7 Deleton The statiors* Techncal Specticziors references were deleted.
. A-8 Deleuon Section A.12_3 A-8 Deletion ' The barred text was deleted. '
t & T&M c;= '---='--- d -P NCO f*H contain a somewhat sindar p r- _m. y .,
m.y 7 -
Ackktion The bold text was added.
Sections 12.4 of each etation's RETS contar a somewha smiar provissort A-9 Deletion The stations' Techncal Spmic tions references were deleted. ,
- A-?O Addaion Added (see Section A.3) in Applicsion statement. i A-11 Deletion The barred text was deleted. i
! "- T&M Sp:'-: _=--s d -~^ CEO "" contain a somewhat .
, sanilar provissort F~ ~~~ Wer, m M '^=--4 rMt?m:
Addtson The bold text was added. l t
l Sections 12.4 of each station's RETS contain a somewhat smiar provisson. !
l Deletion The statiens* Techncal Spain, uu 6 references were deleted. ,
- Section A.1.2.4 A-11 Revisaon The text on p A-12 is unchanged and found on p A-11.
A-12 Addstion Added (see Section A.3) s1 Application statement.
t Section A.1.3.1 A-12 Deletion The barred text was deleted. j l The T&M c r d e-+ CECc station contain a somewhat !
t
' ~
smiar provassort F~ -- ---J :n , --- 5 " - ~ : _ g r;--:'~M: -
[
, Addition The bold text was added. i Sections 12.4 of each station's RETS contart a somewhat sardar provissort ;
A-13 Deletion The stations
- Techncal Specfications references were deleted.
A-14 Deletion The barred text was deleted.
"-- 7~^--~*8
,' c"~% r 9 ee CECe ~~% contas1 a somewt* !
j smiar provissort c~ - r~ rm, m 5 "7: . cg re?M:
j Addition The boid text was added. l j Sections 12.4 of each etation's RETS cortain a somewhat smiar provison.
l Deletion The statens* Techncal Spectications references were deleted.
I Deletion Deletem
. t I
t i -
1
_ - _ _ _ _ _ _ _ _ _ _ _ _ __________.__1 .__
, Appendix A Cont'd ,
- Section A.1.32 A-14 Deletion Tre barred text was deleted.
! 5 T~^~-9 ?MM% d e9 CECc ??" contan a somewhat smilar provesort 9 -" -~91.---. r~- M % r@MW:
Addition The bold text was added.
i Sections 12.4 of each station's RETS contan a somewhat similar provsson.
l A-15 Deletion The stations' Techncal W o references were deleted.
Revsson The text on p A-16 is t .cIwived and found on p'A-15.
A-16 Deletion The barred text was deleted.
!" % T~'- " M~% d ^~^ CECe ??M contain a sonnewis smlar provsson. Fr --* -- ' - . . _ ^;, : - - 5 "- t 5;= "-- "H s Addition The bold text was added.
Sections 12.4 of each station's RETS contain a somewhat smiar provsaort Deletion The stations
- Techncal Spout = inn references were deleted.
Section A.1.4. A-17 Deletion The barred text was deleted.
5 T~^~ " ?p: '-- ^ ' c d e-* CEO -*P. W9 a somewhat
, smiar provssort 6 -- -~_' -.. -.1, r~- M " R 'c; 5;- :'-- " N :
Addition The bold text was added.
. Sections 12.4 of each station's RETS contain a somewhat smiar provsson.
- Deletion - The stations' Techncal Spauin,.iions references were deleted.
4 A-18 Deletion Deleted CECe l
A-20 Deletion The barred text was deleted.
5 TL. _ - _ M SM--?-- - M e~* CEe ?-M contain a somewhat similar provssort Fr --* -- ' _ ._. , r~- M -: -: . _ g - - -?--
- _ - c:
Addition The bold text was addect Sections 12.4 of each station's RETS contain a soirswid similar provsaort Deletion The stations
- Tm.i k.oi Specfcations ivivies w were deleted.
l 4
4
Appendoc A Cont'd A-21 Addtion Inserted pomihesis around the DFGi units [(mrem /hr)/(pCi/m2)].
Section A.1.4.1 Revson Revsed Section 4.1.6 to 4.1.7 in the (D/O), defirwtort A-22 ~
A-23 Revision Revsed Section 4.1.5 to 4.1.6 in the (X/Q), definitiort Section A.1.4.2 Revision Added dcXs above the symbol 1, rate of ingested actury, in Equation A-18.
Section A.1.4.3 A-24 Addaion Added hyphen in radonuclides in D'**,, derntion.
A-25 Addaion Inserted Rate of Ingestion of for L~;e. in the defatiort Revs on Added dots above the symbol I, rate of ingested actuity, in the Equations A-19 through A-22.
Addaion Added See Tables D-6 and D-7 of Appendix D in the Weathenng Decay Constant, Section A.1.4.3.1 A-27 J., in the derntiort AGO Revson Revsed Techncal Spectication 3.112.2 to 3.11.2.1.
Section A.1.5 A41 Deleton The barred text was deleted.
W TM4 Sp'WW_ d e_e CECc d?% contain a somewhat similar provsiort F~ &r r~;9er, em !N f9W egRrims; Addition The bold text was added.
Sections 12.4 of each station's RETS contain a somewhat simdar provsiort Deletion The stations
- Techncal Spectications references were deleted.
Revson Revsed Techncal Specications to RETS.
Deleton Deleted CECO Revsion Revsed specications to RETS.
Deletion Deleted Ceco A-33 Deletion The barred text was deleted.
W TMd SpR?WE d c_9 CECO dTM contain a svir,ewh4 senaar provmort F~ &M r~pWc, c~'!N fem r~xRT ~r:
Addaion The bold text was added.
Sections 12.4 of each station's RETS contain a somewtiat smilar provmort
( The stations
- Techncal SpecIcatiors references were deleted.
Deletion Deletion Deleted CECO Revision Revsed Techncal Specicatons to RETS.
Secton A.1.6 A-34 Revson .
Deletion Deleted CECO Revson Revsed *specfcations* to " sections".
Revson Revsed Braxfwood Techncal Specications Section from 3.1124 to 12.4.4 Revision Revsed Byron Techncal Specications Sections from 3.1124 to 12.4.4.
Revision Revsed LaSale Techncal SpecEcatons from 3.1125 to 12.4.5.
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~
Section A22 A4 Deletion ' The barred text was deleted. .
- % Te-' ?@?M d -~^ CEe -*?jen cortari a somewhat i
semiar pronssor ' r~ -~* --_^ _ . . . .C, r r S " " ; _ g r~- ' - --- 1:
. Addnion The bold text was added.
[
Secuans 12.3 of each station's RETS cortain a somewhat sanilar pronsson.
j- Deletion The stahons' Techncal Sp-5 iions references were deleted.
[ Rensson Rensed Techncal Specficahons to RETS.
[ A-40 Rensson The text from p A-40 is fotsid on p Am.
Rewsson Revised TechncalSp.4= uons to RETS on page A-39.
[
lL Deletion Deleted CECe on p Aa.
l A-41 Deletion The barred text was deteted.
[
% T -:^ 9_-M ?P-M d e-* CEe -**M contain a somewhat smiar pronsaxt Fr -w --J _. ._ c -- e _ c; -:---
- - r+1
Addneon Tha bold text was added.
Sections 12.3 of each station's RETS contain a somewnat smiar peonseort Deletion Tile stanons* Techncal Specfications references wees deleted Deletion Deleted CECe Rension Rensed Techncal Spali iion to RETS.
Section A2.4 A-43 Deletion Deleted CECO.
l Addaion Added Also refer to I =9mE= 1/2 RETS Sec6on 12.3.4.
l Section A2 5 A-43 Revision The text from p A-43 is t==Jy upd and is found on p A-44 2
d A-44 Deletion The barred text was deleted.
l % T-2 2 ?p-M d -~^ cme -*9 cortart a somewhat similar provissort Fr :? --J _.. _c; - t t :--g p '--M--5:
l Addition The bold text was addect
- Sections 12.3 of each station's RETS contain a somewhat smiar pronssort Deletion The stations' Techncal SpmJ iions references were deleted.
Revision The barred text was deleted.
j Each station except Zion is requred to protect doses due to Equid
- releases at least once per 31 days 'r-- S'M ?,r, W ' -c-"- -
l
? f ~ M ^***1*-~' & 22 -~* ?_ ' C % ? ? ? M ^n ?.y.
Zion is required to proyect doses due to Equid releases at least once a month Cr Te Spe ' * * ' A1).
I s
Appendix A Cort'd .
A45 Revision The text from p A45 is unchanged and is found on p A44.
Section A2.5 A45 Revision The bold text was insened and the barred text was deleted.
Section A26 -
M Five stations (Braidwood, Dresden, LaSale, Quad Cties, and Zion) have requremerts for calculation of dnnking water oose that are related to 40CFR141,the Ermronmertal Protection Agency Natir.nal Prmary Dnnking Water Regulabons.
Section A3 A-45 Revruon The barred text was deleted and the bold text was inserted.
^T=W M Sp~P:T&cdcf ECec?&
Eacf: station's RETS contan a somewhat similar provenort For exact requeaws, see the foaowng spec (cations-Rerson The barred text was deleted and the bold text was inserted on p 45.
A46 Braidwood 1/2: 3414 12.4 Byron 1/2- 344,4 12.4 A45 Addaion LaSalle 1/2- 342,4 12.4 Dresden 1: 12.4 Dresden 1/2- 29 ^ 2 d, ? 9 ^ ? d, ? 9 9 2d 12.3 and 12.4 Quad Cties 1/2- 2e
- 2d, ? ?.1? d, ?AE.2d 12.3 and 12.4 Zion 1/2- 2?22 A W 9 (c^^ ~~~"?~* A?% & b 2~J c}.
12.3 and 12.4 A47 Revruon The text from p A47 is i .lsyed and is found on p A46.
Revenon Revised Techncal Spec (canons to RETS.
Deletion Deleted C&Co Revepon Revtsed Techncal Specfcations to RETS.
A-50 Revenon The barred text was deieted and the boki text was inserted.
Section A3.1 For the Braldwocd and Zion stes, whole body dose cuuuTairient due to consumption of dnnking water from the communty water supply supplies nearest the stations.
A-51 Deletion Inserted the. Deleted CECe 2nd inserted "four*.
A-52 Deletion Deuted Ch Section A.32 A-52 DeLition A-53 Deletion Section A.3.3 A-55 Deletion Revruon Revsed refemnce from Secton E11 to E11.2.
Deleton Deleted C&Ce anc inserted
- Station
- in Secuon heading A.42.
Section A42 A-56 Revrpon Revised Techncal Specifications reference from 4.8.B2.b to Secton 12.3.
1
Appendoc A Cont'd
- j. ,
Section A.42 'A-57 Deletion Deleted Techncal Specircanon reference 1 ? * ? 23.
Rewisson Revised Techncal Speceirmenn reference 3.112 to Secton 12.3.
- Deletion Deleted Techncal Spec 5icanon reference 1? ? 2A?.
, Section A.4.3 A-57 Rowesson Deleted Ceco and insened OOCAR.
Delecon Deleted tsy-CGCo.
j Table A-1 A-58 Deleton Deleted N.
j Revision Revised Zion Techncal Spec 5icahons reference frorn 3.12 and 4.12 i to Secnon 12.4.
I Table A-2 A-59 Delenon Deleted *.*i- ^:I W Te " " -- e^ ^ ".
! Revisson Revised *Peone,121 river rntes* to N 4 river maes*.
Revised other CECO Nuclear Stanons from *DNPS and LSCS* to "None*.
[
( Rewisson Revused footnote from *a" on p A-59 to *c' on p A-60.
! Addmon Footnote a ongriaBy provided riforrnahon on radwweve Iquid emuert flow -
! paths downstreamfrom Byronand Quad Caes Stamons. Now the referencedirectsthe raariar to Table E-2 of Appendsc E.
i s
i i
}
t i
1
. _ - - - - _ ._ . . _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _. _ _ _5
Appendix B B-i Revson Revsed Section B.S.3 from p B.30 to B-31.
Table of Cornerts Addition Inserted 7 after DFG,in Section B.8. .
B-1 Addnion The ooid text was inserted.
These are used to account for the release of radioactMiy to the erw=& simit and the exposure of persons to it.
Section B.1.1 B-3 Deletion Deleted Ch B-3 Deletion Deleted *s' fosowrig JFD.
Section B.12 l
B4 Deleton Deleted Ceco, Section B.12.1 Section B22 B-12 Revson The bold text was inserted and the barred text was deicted in the X. defrwon.
The trne-average concentration of airborne radcactuity in a sector eMhe at ground level at a drance X form the release port.
B-14 Addtion inserted at ground level in (X/Q), definition.
Section B.3.1.
B-17 Addstion inserted units, [1/sec'] in S definitiort Section B.3.1.1.1 Section B.3.1.12 B-18 Deletion Deleted Ch B-18 . Addtion irsetted at ground level in (X/Q), defruticrt Sectirm B.3.2 B-20 Addition laserted at ground level in (X/C), derrwiott Section B.3.3 B-21 Revision Revsed *h/ to *ft* in Equation B41.
Section B.4.1 B-22 Revson Revised *h/ to *tt* in both D, and h, derrutions.
Addition Inserted ' effective" before release beghts in D, and h, defMions.
Revsson Revised 'tharf to *therf in D, derrutiort Revsson Revsed
- actual" to *effectue* in h, derrutcrt Section B.4.3 B.23 Rovson Revsed *h/ to *tt* in EMion B43.
B-25 Addstion Inserted at ground level in Si derrvtsort Section B.S.1 B-27 Revsson Revsed RG reference frorn 1.111 to 1.109 in f( ) definitiott B-27 Addition inserted at ground level in G definitiort i
Section B.52 B-28 Addition Inserted at ground level in Vi definciort Section B.S.3 B-30 Addtion trsetted at ground level in Si definitiort Section B.6.1 Addsion Inserted *g/* in 5 cm in t, definhiort B.30 Addition Inserted at ground level in G, de"riitioet Section B.6.2 B-31 Addtion inserted at ground level in V, definitiott Section B.6.3 B-32 Addstion irserted T after DFG,.
Section B.8 B.32 Revision The text frcm p B42 is unchanged and is found on p B-33.
Section B.9 B-33 Revision The text from p B-33 is unchanged and is found on p B43a.
Section B 13
~
Appendix C ,
C-1 Deletion Deleted Ch
~
Section C.1.1 C-1 Addition inserted parenthess around (U"M*/F7 in Equation AM C-2 Deletion Deleted *1/* in (1/M) in Equation C-1.
Addition Inserted parenthese around (M/F) in Equation C-2.
C-3 Addaion Inserted parenthess around (M/F) in Equation C-3.
Section C.1.2 C,3 Deletion Deleted Ceco.
Addition Inserted pi-wiiiisis around (UM/F') in Equation A.31.
Section C.1.3.1 C-4 Revsson The bold text was inserted and the barred text was deleted.
The values of dilution flow rate F. addeenal dilution l factor 1/M, and decay penod t can d5fer for water and fish.
l Section C.1.3.1.1 C-4 Revsson The told text was inserted and the baned text was deleted.
For the purpose of < maridering the drinking water dose from i liquid effluorits M iged into a river, tl ' sassumed that total meang of the E==ga in the river flow (F")
occurs prior to consumptiort The meneure of dilution used parameter 1/M", and may be thought of as the fracdon of
! full river flow in which diludon occurs. "l/M"=1 iv : % -
full dilution.1/M"less then 1 represents dilution in only a 4
portion of the river.
Section C.1.3.1.2 C-S De:etion Deleted CECO.
- Deletion Deleted addsson.
Section C.1.3.3 C-6 Revson Revsed 'A," to 'A,*.
Section C.1.3.4 C-6 Revision Revised Table reference from D-8 to 12.
i l
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Appendix E -
Addition irsetted
- Introduction to* in Section heading E4.
E-i Deleted by CECe in Section heading E4.4. ;
Deletion ~
Deletion Deleted *s* in Measuremerts in Section heading ES.
Deletion Deleted Ceco in Table heading E-6.
E-iv E-1 Revision Revsed the Chapters 1 through 9 to 8.
Section E12 E-3 Revision The bold text was added and the barred text was deleted. I The use of historical average atmosphere condtions for assessmert of radiation doses due to arborne effluerts is st(xdated in the Bases Section 12.4 of each station's RETS
= MW.
Deletion The stations
- Tectncal Specircations references were deleted.
Revision The bold text was added and the barred text was dMed.
This requiremert is cortamed in the Braidwood, Byron, and 23on Stations
Deletion The stations' Techncal Specircations references were deleted.
E-4 Addaion Deleted CECO nserted The stations.
Section E3.1 Inserted comma followog upper Mississippi River basin.
E-5 Deletion Deleted CECO three times.
Section E32 E-6 Revson The text frorn p E-6 is urd ged and is found on p E-5.
Section E3.3 Deletion Deleted CECO.
Revision Revsed 'plart* to
- stations".
E-7 Revision Revsed 'this* to *these".
l Deletion Deleted Ceco three times.
E.8 Deletion Deleted Ceco Addtion irserted
- Introduction to* in the Section heading E-4.
! Section E4 E-8 Revision Revised "see* to
- compare *.
Section E4.1 E-9 l Deleted d %2'& dce c^ mtm~*.
Deletion l
l Addaion irsetted with Equation A-17 of Appendix A.
( d Section E4.3 E-10 Addaion Inserted X = (1/3.982E-5 cm )(1 ft/30.48 cm) = 823.9 ft.
f Deleted CECO from tha Secton headog E4.4 Section E4.4 E-11 Deletion Revison Revised *consideratiorf to *concerrf.
Deletion Deleted 6/ CECe.
E-12 Revcon Revsed LaSa5e Table 4.112-1 and Zion Table 4.12-1 to Section E4.5 12.4 for both stations.
__- J
Appenda E Cont'd -
Section E7 E-12 Deletion Deleted Ceco Section E8 E-13 Delet6n '
Revision Revised hachncal Sennees Nuclear Sennces* to *NSEP".
Section E9.2 E-14 Debtion Deleted Ceco Section E9.3 E-14 Dele' ion Section E9.4 E-1C Deletion Revsed *in radians
- to at downwind dstance x* h the second txAet of Ecpation E-5.
Section E9.5 E-16 Revision E-17 Deletion Deleted CECO.
Section E9.6.1 Deletion Delete extra penod fonowing Section 4.1.4.
Section E9.9 E-22 E-25 Add. tion inserted T after DFG,.
Section E9.15 E-26 Deletion Deleted Ceco Section E9.17 *
- E-27 Deletion E-28 Deletion Deleted Ceco Section E10.1 Addition The boid text was inserted and the barred text was deleted.
For drinking water, withdrawn of Byron, Dresden, LaSalle and Quad Cities Stations, ttus model assumes complete snarxj of stations' discharge with river water before withdrawal as potable water. This is based on the existence of one or more dams between the station liquid dird-gu and the water supply intake point. For drinidng water withdrawn downstroom of Braidwood Station, this model assurnes partial mixing of the Station's discnarge wfth rtver water before wit!wirawal as potable water. (See Table E-6 of this Appendir).
For fish, the river model assumes complete mixing in the a near4ield river flow (F'). M t_ r; M Mr P~M $_' 5 f
d !M 9~. M 2M 5 'M p~9; M 'We meeg
- m y'M p M . % v9r 9!M ~'-~TW 5 k br^d ~'N T M .
Revision Revse for a
- maximum
- to the *maximaDy* exposed rximdual E-29 E-29 Deletion Deleted CECO Section E11.1 E.31 Deletion Deleted Ceco five times.
Section E11.2 Revson Revsed Bases Section *3/4.11.4* to *12.4* for BraidwoodByron and to 12.4* for Labase.
Em Deletion DeletedCECo i
Appendoc E Cont'd .
Revson Revsed *Peona,121 dver maes* to "WilrTungtion,4 ruer maes".
Table E-2 E-34 Deletion Deleted IEinces R. as a recemng body of water for Bradwood.
Deleted irierences to recreation and irngation actmties.
Deleted the Note abott the Kankakee R.
Revson Revsed reference footnote wth updated =;tudy.
Table N-2, Note b E 35 Revson Revsed reference footnote wth updated M W.
Tabis E-2 rJote k Revson Revsed Braidwood dose values to renect currett study.
Table E-3 E 36 Table E4, Note a Revbion The bold text was inserted and the barred text was deleted.
Per Braicwood ER, Table 5.2-7. and Reference 81. Except for NN potable water and fish p^^ F~'Tc Q, these values are based on water in the dsde go canal For potable ws.ter, the point of consumption is Wilmington, IL For Tsh, t is assumed that they are caught in the Kankakee Ruer.
Table E.3, Note d E-37 Deneton Footnote d was deleted. Footnote e was revued to e.
E-41 Deleton Deleted Ceco in table heading E-6.
Table E-6 Revsson Revsed *Peona,121 river miles' to *Wtrrungton,4*.
Remon The sertence regardrig Kanakee River flow into the I:roois was relocated to the second buDet.
J
Dresden .
Chapter 10 10-1 Addstion The new indces desgnations are idertried on page 10-L Deletion Deleted Genero in the page tale. ~
Revsion The Table of Cortents are carned over from p 10i to p 10-i.
Table of Contents 10-i 10-iii Revision The List of Figures am carried over from p 10-3 to p to-iii.
List of Figures 10-2 Deletion Deleted period in f, definition.
Section 10.12 Deletion Deleted penod in O. dersntiort Deletion Deleted penod in 0,, derancon.
Addaion Inserted Table 12-2-4 of.
100 Revsson Revsed Techncal Specreations to RETS.
Section 10.12 Revsson Revsed Caction 1.0 to 12.1.
Deletion Deleted d & TrWd SgfrMh Revsson Revsed the number zero to the letter 'O' in butterfly vakes i.d.s.
Section 10.1.4.1 10-9 Revsson The bold text was added and the deleted text ba:7ed-The recorder, controls, ind~cator and trip unts, alarms, and annunciators are located on the 902(S)-2. 902(3}-3, and 902(3}-10 902 2 2M T210 paneis in the main cortrol room.
10-14 Revsson Revsed Tables 4.20 and 42-2 to 122-2.
Section 102.2 Addition The bold text was added.
Liquid radioactive effluents are not released from Unit 1 storage tanks directly to the environment but are made tnrough Units 2/3 Radweste System.
i Revision Rev: sed Techncal Specreations to RETS.
l l Revision Rev: sed Section 1.0 to 12.1.
Deletion Deleted d h TeW* Smfe?h l 10-16 Addition The bold text was inserted:
Section 102.5 The dhcharge valve is locked closed at all times except during the discharge. All other lines which tie in with the discharge line are locked closed. The high and low flow Revision Revsed radwaste 'foremart to 'supervsor.
Addition Inserted a comma following system assembly and before identfication.
Section 102.7 10-17 10-18 Revsion Revsed Techncal Spectications to RETS.
Section 10.2.8 I
Dresden Cont *d Chapter 11 ' 112 Addeon The new Irdces deoegnmeone are ident5ed or, page 114 Deleton Deleted Genene in the page tee. [ -
Table of Cortents 114 Rowson The Table of Coreents are camed over kom p 11-4 to p 114L List of TobAee 11-iii Rowe.on The Ust of Tabies are camed over from p 114 to p 11-iit ,
Detof Figuree 114v Revisaon The Det of Fegssee are camed over kom p 11-iii to p 11-iv.
- Tobie 11 1 11-2 Deleton De6eted gamme koonope enehsie on quarter *y as sampio pereculate l composeos.
11-5 Reesion Revised ' Gross
- to *Gemmt motopc in Lase Weeer Type of Anahe.e.
Roweson Remoed montreng locaton, the distence and beenng, for ground met water, i D 23 Thorsen We# tom 2.0 mi N (12 km A) to (L7 mi S (1.1 pm 4 Roweson Rowtood *Gammt to *Grcoe* been in Grourdwas Water Type of Analysis.
, 11 4 Roweson Rowneed the mik earnpiis33W=m~t, D 26, see tom Troser to Helpne's Dary, t b 11-7 Floweson Renood Emergency PW Superwect to Emergency Preparednese Drector I in Footnote e.
Chapter 12 1
New insert Appendix F i F4 Addison The new irdces designmeons are idensed on page F4 Do6eton Doested Generic in the page zee.
Table of Conter ts F-il Reween The Tabee of Consente are camed over kom p F 4 to p F-il
- Ust of Tablee F-iii Rowte.on The Det of Tabies are camed over from p F4 to p F4ii.
- Ust of Figuree Fu Redsson The Ust cf Figurae are camed over tom p F-iii to p FA.
, Secton F-2 F-1 Addeon inserted the bold reference.
- 1. sargent & Landy, me secesverde and usensing newesien er - _ ,
- Appenses I Toceanicei & Tahion,* Reetatert 2. July 10,1970-Tobie F-1 F-2 Addeon Added *s* to
- Parameter
- in the Water and Fish Ingeston Parameters hoesng Tab 6e F-3 F-4 Roweson Remoed the Neerest Resident cEseance trom 1000 to 986 m in the ENE drectort De6eton Deleted the barred tout below sn Footnoes a. l
, w t_
- ; g- _; .w> - u m- r e m i ey e_ m m - as - n ynea*7 Roweson Rowse Secton A2 4 to A1.2 in Footnote e. Updened annual surway to 1990L Addeon boorted *A* fosoenng Appends in Footnote tt Tab 6e F-4 F-5 Addiron heerted the *s* in Reference, and also *and 2'in Focenote a.
Addeon Added the beid tout as Focenose tt .
The salmed neede salues apply only to Droeden 2/3. REmed anode wives are not needed See Droeden 1 since Wiere le ne enhead neede reisees petr=t.
Tabie F-5 F-7 Rows ori Revised Reference *t* to *2* in Note 1.
Table F4 F-9 Revision .
! Table F-7 F-10 Addeon Inserted *a* in Reference, and e6so *and 2* in Note 1.
Table F4 F-40 Revieson Rowsed the dih, f( trom 1000 to 966 trt I
e
4.3 MAJ0ft CilANGES TO Tile RADIDACTIVE WASTE TREA*1hENT SYSTEMS during June 1991 Unit 2 and Unit 3 Itcactor Building Floor Drain Stunp l' ump ilun Timer Modification packages have been teleased to the Operating Department.
Also, the Unit 2 and Unit 3 Drywell Equipment and Floor Drain Sump Pump Itun Timer Modification packages have been released to the Operating Department.. Four of eight Turbine llullding Sump Pump Itun Timer Modiflentions have been completed, and the remainder are scheduled to be installed and tested in August, 1991. The Itadwaste Precoat Area Sample Sink installation is scheduled to start in September, 1991. The Tank lloom pipe replacement continues with tie-ins to the new Waste Collector and Floor Drain Collector Tank Inlet lleaders.
4.4 FAILED FUEL ELJ. MENT INDICATIONS 4.4.1 Unit 2 Dresden Unit 2 fuel performance during June 1991 continued to show no indications of Icaking fuel. This is bases on the sum of the activities of the six noble gases as measured at the recombiner. liased on the reported data. Unit 2 had excellent fuel perf ormance.
4.4.2 Unit 3 Dresden Unit 3 fuel performance during June, 1991 continued to show no indications of Icaking fuel. This is based on the sum of the activities of the six noble gases as measured at the recombiner. liased on Llie reported data. Unit 3 had excellent fuel performance.
ZR18/1463/14
i 5.0 P LANLOll i ROC EWRILCilANG E S . _IESTS . . FJP ER IMENIS . _Ni1L S A FEILEE1AT ED t1All41ENANCE 5.1 Amendments to Facility License or Techniu.i Specifications.
No new amendments to incility license or Technient Specifications were approved for use during June, 1991.
5.2 Changes to Procedures Which are Described in the FSAR (Units 2 and 3) during June, 1991.
Table 5.2.1, attached, sununarizes the revisions to procedures described in the FSAR which were approved during the June, 1991 reporting period.
ZR18/1463/15
^
E IAR_IJ 5.2.1 CHANGES TO PROCEDURES WHICH ARE DESCRIEED IN THE FSAR (UNITS 2 AND 3) FOR June, 1991 FROCEDURE TITI.E/ DESCRIPTION START OF FROCEDURE TYPE FROCEDURE NO.
C*i MGT.S 2
Dresden Instrument DIF 0700-04 IRM Rod Block / Scram Calibration Test Surveillance Procedure 2,3 Dresden Operating DOS 0500-01 Manual Scram Circuit sensor Test Surveillance Procedures 1
DOS 2300-03 High Pressure Coolant Injection (EFCI) System Operational Verification NOTES: 1. Administrative change; intent of procedure tu2 changed.
- 2. Changed for clarification, intent of procedure unchanged.
- 3. Changed to incorporate requirements for new equipment; intent of procedure unchanged l
j 4 Changed to implement improved testing / calibration methodology; intent of procedure unchanged.
l l
ZRIS/1463/16
- l 5.3 Significant tests and experiments not described in the FSAR (Unita 2 & 3)
Significant special procedures involving tests not described in the FSAR I which were approved during the month of June, 1991 are listed below l SP 91-05-65 TEMPORARY DULLER TEST The purpose of this procedure was to test the operability of the-temporary boiler and verify proper steam pressure j at the Nitrogen Vaporizer.
SP 91-05-68 CONSTRUCTION ACCESS FACILITY SERVICES MODIFICATION TEST M12-2/3-87-002L The p"rpose of this procedure was to detail the steps necer'try to verify that the Rad Waste Upgrade Construction Acces, l'acility lighting fixtures, emergency lights, unit heaters, welding receptacles, duplex receptacles and air flow ope- te per design.
SP 91-06-69 MODIFICAT10ll TEST FOR M12-3-88-063 The purpose of this procedure is to provide instructions to test the Motor Optrated Valves (MOV's) modified in Modification M12-3-68-063, 2 to 4 Rotor MOV Limit Switch replacement.
SP 91 70 DIESEL GENERATOR FUEL CONSUMPTION TEST The purpose of this procedure is to obtain data points on the Diesel Generator fuel consumption rate which will further substantiate the results of previous testing.
SP 91-06-71 UNIT 1 PANEL 901-B1 ANNUNCIATOR TEST FOR MODIFICATION M12-2/3-87-05G The purpose of this procedure is to perform nn independent overview of Operational Analysis Department (OAD) construction testing of Modification M12-2/3-87-05G.
This overview will verify operation of the annunciator
- system associated with Unit 1 Control Room Panel 901-Bl.
SP 91-06-72 IIPCI MOV 3-2301-10 VIBRATION DATA COLLECTION The purpose of this procedure 3, to install four accelerometers to record vibration data from the the MOV 3-2301-10 valve while performing the Quarterly Inservice Testing (IST) portion of DOS 2300-3, liigh Pressure Coolant Injection (llPCI) System Operability Verification. This data will be used to assess the feasability of a new multi-trim MOV 3-2301-10 valve which is planned for installation during the D3R12 refuel outage.
SP 91-06-74 INSTALLATION OF RELAY TREE ON Tile C STRING OF Tile MAIN STEAM LINE (MSL) TUNNEL TEMPERATURE SWITCllES The purpose of this procedure is to install a relay tree onto the C String of the MSL tunnel temperature switches at junction box 3TD-B18. This will provide a means to determine which of the four temperature switches within the C String has tripped, causing a recent spurious half primary containment Group I isolation signal.
5.4 Safety Related Meintenance (Unit 2 and 3) l Safety related maintenance activities fe,r June, 1991 will be atmanarized in the July, 1991 Report.
2R18/1463/18
S.6 Temporary System Alterations Installed (Unit 2 and Unit 3)
A " Temporary 5, stem Alteration" refers ,to electrical jumpe lifted
, fuses moved f rom normal to reserve holder, temporary power supplies, test switches in alternate positions, temporary blank flanges, and spool yieces.
Alterations controlled and documented as part of a routine out-of-service or other procedure, alterations which are a normal draining process are not included. feature of system design, and bases I 5.6.1 Unit 2 June, 1991 Temporary System j
A11erativLRh Descript.ipn Installation Removal
____Dete J ate _
II-23-91 This temporary alteration re-routed 06-14-91 the Unit 2/3 Cribhouse upper level 3 Months sprinklersby isolating the sprinkler ,
system, cutting the existing piping I back 9 to 10 feet and threading the ends, re-attaching the sprinklere and opening the isolation valve.
This was accomplished to provide regoired cleerances for modification of the Cribbouse rolley beam.
II-24-91 This temporary alteration installed a 06-15-91 Fermanite seal on an elbow of line 18 Months 2-3013-2 1/2-B to stop a pin-hole leak.
This was done to prevent e sacuum leak into the Main Condenser. !
11-25-91 This temporary alteration installed a 06-25-91 corrosion coupon rack on the D2 RBCCW 3 Months system near the Feedwater Sample Panel to monitor effectiveness of the Chemistry Control program.
5.6.2 Unit 3 June, 1991 Temporary System InstallationJht. Deact.iplion Installation Removal III-04-91 . Dali___ _Da te__
This temporary alteration installed a 05-31-91 Gordon instrument to the terminal 3 Months blocks of computer point A3854, Drywell Radia tion til ' A ', to drive the computer point downscale.
Radiation Monitor operability was not affected and only the computer point was altered.
III-05-91 This temporary alteration installed a 05-31-91 Gordon instrument 3 Months of computer point A1072 to the Drywell terminal blocks Radiation 111 'B', to drive the computer point reading downscale.
Radiation Monitor operability was not effected, and only the computer point was altered.
ZR18/1463/20
5.5 Completed f;afety Related Modifications (Units 2 and 3)
Only modifications which have been completely closed during June, 1991 are listed; modifications which are authorized for use but not completely closed will be reported based on the date of their final closure. For ease of reference, the changes have been identifled by their design change control modification number.
Moditication_No llestr. int _ ion None N/A ZR18/1463/19
Temporary System Alterations Installed- (Unit 2 and Unit 3) 5.6 A " Temporary System Alteration" refers to electrical jumpers, lif ted leads, removed fuses, fuses turned.to non-conducting position, fuses moved f rom normal to' reserve holder, temporary power supplies, test switches in alternate positions, temporary blank flanges, and spool pieces. Alterations controlled and documented as part of a routine out-of-service or other procedure, alterations which are a normal feature of c; stem design, and hoses installed as part of a venting or draining process are not included.
5.6.1 Unit 2 June, 1991 Temporary System Installation Removal ALLeration.Eo2 Description Date l le_
II-23-91 This temporary alteration re-routed 06-14-91 3 Months the Unit 2/3 Cribbouse upper level sprinklersby' isolating the sprinkler system, cutting the existing piping back 9 to 10 feet and threading the ends, re-attaching the sprinklers and opening the isolation valve.
This was accomplished to provide required clearances for modification of the Cribhouse rolley beam.
II-24-91 This temporary alteration installed a 06-15-91 18 Months Fermanite seal on an elbow of line 2-3013-2 1/2-B to stop a pin-hole leak.
This was done to prevent a vacuum leak into the Main Condenser.
II-25-91 This temporary alteration installed a 06-25-91 3 Months corrosion coupon rack on the D2 RBCCW system near the Feedwater Sample Panel to monitor effectiveness of the Chemistry Control program.
5.6.2 Unit 3 June, 1991 Temporary System Installation Removal Installation _Hoa Descriplion Date Date III-04-91 This temporary alteration installed a 05-31-91 3 Months Gordon instrument to the terminal blocks--of computer point A3854, Drywell Radiation Hi 'A', to drive the computer point downscale.
Radiation Monitor operability was not affected.and only the computer point
.- was altered.
-III-05-91 This temporary alteration installed a 05-31-91 3 Months Cordon instrument to the terminal blocks of computer point A3072, Drywell Radiation Hi 'B', to drive the computer point reading downscale.
Radiation Monitor operability was not effected, and only the computer point was altered.
ZR18/1463/20 l
4 t10tlH1LLELPORLDLf RUDUCIl0!tl VEL 0ll REPORTING AREA _itaupn_#1LQttaden l3lDIESELIUELOIL l lIGN1110NTUELOIL HONTH Jw t, % l]lGASTURBINEFUELOlt l_l JET-ENGitlEFUELOil PURCHASE ORDER ItN01CE APPROVAL GALLONS
_]M1DLL
-- t{gne __ -
A. INVENTORY - BEGTNNING OF HJHTH 46.182 B. TOTAL GALLONS IPN01CED , O C. TOTAL GALLONS RECEIVED UQI INVOICED Q 0 tilW5:
D. TOTAL GALLONS CONSUMED _MR E. TOTAL GALLONS tl0T ItlVOICED IN PREVIOUS HONTH J _Jf>4Q F. INVENIORY - END OF HONTH 45,614 cc: D. C. Maxwell STATION FUNCTION NUMBER 33,153 _ _ MANAGER - '
ZR10/1463/22
Commonwealth Edison
- , . fj c. Dresden Nuclear Power Station 1 0- - J RR#1
[ Morris tilinois 60450 Telephone 815/942-2920 July 1, 1991 EDE LTR: #91-426 To: Robert Mackenzie Fossil Operations Edison Bldg., 211E
Subject:
Dresden Station Nuclear Fuel Consumption, Fuel Oil Therms and Auxiliary Power for the Month of June, 1991.
Unit _2 Unit _3- ..
Nucient Therms _38.h 25.. 808,.9 L 3Z.32 Z.84 L 38 J,.
-MWL Days 464911.08 45.blft 11_
Therms Diesel Oil 441 443 Gallons Diesel Oil _ 324 324 ,
Auxiliary Power Lift Pump __ 2.106 _ l .957_ _ -
Sprays and Lighting ZL bM la Prepared By: 0* $
D. C. Maxwell Technical Staff Approved By: '
- E. D. Eenigenburg Station Manager Dresden Nuclear Power Station EDE:DCM:dwh cc: C. Larson Comptroller's Staff D. C. Maxwe11 File /T.S. File Flie/TSN File /Nwnerical ZR18/1463
=
, i ,9 Generating statistics for month of ..Junc.,._1991_ __ for (name of unit) Dresdcn_Il Gross MWil thermal produced in month ._ .125.866_ __ ._ _ _ _ _ _ _ _ . _ _ _ _ _
Gross MWil electric generated in month _ 3AZ 320 _ . _ ,
Net MWil electric generated in month _._325.934 Availability (turbine) for month _S2 11% Equivalent (energy) avallability for month ._15.107, for year through month's end 5.2.16 for year thcough month's end 48.h21 _ _.,__
Adjustments (if any) to previously reported figures or NW listings: _H/A Outages:
Number of nutomatic scrams _. 1 manual scrams _ O_ ____
llours of outage ___36.107 __ Scheduled _ _ _._0_ _._ _ Forced _ All__
Total outages: ____56107__ _ _
Primary reason (s) for downtime: _Ilain_Turb ine_t htus t_ bearing _ wear _de tec t u Lmalf unc t ion._
dutinLauty1111ancL.tes11ngi. _ _ . . _
If the unit was in a refueling outage:
outage began _ N/A outage ended (or estimated startiip date) N/fi Was unit operating in load:Lollowingade, coastdown, or cycle stretchout mode (s)?_Yes_
If so, how many hours? ll;31_
llave you changed your MW ratings?
.N/A _ _ _ MDC Net _ _N/L._ I.icensed MW Thermal Zill8 /1463 / 23
a ., +
a- 4 g,
Geierating statistics for rnonth of June,_193L__ for (name of unit) Dresdettill Gross MWil thermal produced in month 1,0M. L4L Gross FNil electric generated in month __32h,890 . . . _ _
Net FNil electric generated in month ,____30h,l22 Availability (turbine) for month 10n,.01 Equivalent (energy) availability for month _Bidl_._
for year through month's end Bh38% for year through month's end 77.41%
Adjustrnents (if any) to previously reported figures or NW listings: J/A Outages:
Number of automatic scrams Q manual scrams 0 llours of outage 1 Scheduled Q Forced 0 Total outages: O Primary reason (s) for downtime: __ _
If the unit was in a refueling outage:
outage began N/A outage endad (or estimated startup date)._ _N/A _
Was unit operating in load-f ollowing mode, coardom, or cycle stretchout mode (s)?_JES__
If so, how many hours?._l20;.00 _.
llave you changed your MW .ttings?
__ _N/A_ MDC Net E/A_ _ Licensed MW Thermal ZR18/1463/24
_ -