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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K0641999-09-0101 September 1999 Proposed Tech Specs,Changing Definition of Azimuthal Power Tilt in TS 1.1,correcting Peak Linear Heat Rate Safety Limit in TS 2.1.1.2,correcting Dc Voltage & Degraded Voltage Settings in SR 3.3.6.2 & Correcting Typo in TS 5.6 ML20211G7681999-08-27027 August 1999 Proposed Tech Specs,Allowing Placement of One or More Fuel Assemblies on SFP Rack Spacers to Support Fuel Reconstruction Activities While Irradiated Fuel Assembly Movement Continues in SFP ML20207F0261999-06-0101 June 1999 Third Interval Inservice Insp Program Plan for Ccnpp,Units 1 & 2 ML20195B2751999-03-31031 March 1999 Rev 0 to Rept 98-FSW-021, Corrosion Test of SG Tubes with Alloy 800 Mechanical Sleeves ML20204H6011999-01-29029 January 1999 Age Related Degradation Insp (Ardi) Program Technical Requirements Document for Mechanical Systems ML20196E2191998-11-30030 November 1998 Proposed Tech Specs,Allowing Repair of Defective SG Tubes with leak-limiting Alloy 800 Repair Sleeves ML20195K3831998-11-20020 November 1998 Proposed Tech Specs Removing TS Originally Developed from Reg Guide 1.35 & Implementing Requirements of 1992 Edition Through 1992 Addenda of ASME B&PV Code Section XI, Subsections IWE & Iwl,Per 10CFR50.55a ML20195J7181998-11-19019 November 1998 Proposed Tech Specs 3.7.6, SWS, Adding One SWS Heat Exchanger Inoperable as New Condition for LCO 3.7.6 ML20155F7001998-10-30030 October 1998 Proposed Tech Specs Bases,Revs 1,2 & 3 Re List of Effective Pages for Plant ML20154N1961998-10-16016 October 1998 Proposed Tech Specs Pages,Revising TS 3.3.1 & 3.3.2 to Clarify Inconsistency Between TS Wording & Design Bases as Described in TS Bases & UFSAR ML20198A2981998-09-15015 September 1998 Technical Procedure CP-217,rev 7,PCR 98-034, Specifications & Surveillance,Secondary Chemistry ML20198A3131998-09-15015 September 1998 Technical Procedure CP-224,rev 4,PCR 97-049, Monitoring Radioactivity in Systems Normally Uncontaminated ML20236S5621998-07-20020 July 1998 Proposed Tech Specs Providing Alternate Cooling Water Supply to Maintain EDGs Operability During 1999 Refueling Outage ML20195B2861998-06-0505 June 1998 Rev 0 to Rept 98-TR-FSW-005, Test Rept on Alloy 800 Mechanical Sleeve-Addl Qualification Testing Using Low Yield Strength Tubing ML20217D2691998-04-21021 April 1998 Proposed Tech Specs Re Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging ML20216H0831998-03-16016 March 1998 Rev 13 to Proposed TS Re Conversion to Improved TSs ML20198A2911998-02-23023 February 1998 Technical Procedure CP-206,rev 4,PCR 98-034, Specifications & Surveillance Component Cooling/Service Waster System ML20199J5281998-01-28028 January 1998 Proposed Tech Specs,Converting to Improved TSs ML20198K9851998-01-12012 January 1998 Rev 11 to Proposed Tech Specs,Reflecting Conversion to Improved Sts,Per NUREG-1432 ML20198R7331997-11-0505 November 1997 Proposed Tech Specs Pages Re Rev 10 to Convert to Improved TS ML20217K6161997-10-23023 October 1997 Proposed Tech Specs Section 3.8 Re Change Request to Convert to Improved Std TSs ML20217K6671997-10-22022 October 1997 Proposed Tech Specs Incorporating Both Steady State & Transient Degraded Voltage Setpoints Into Tss,As Opposed to Current Single Degraded Voltage Setpoint ML20198K3321997-10-20020 October 1997 Proposed Tech Specs Section 3.3 Re Change Request to Convert to Improved Std TSs ML20217G3571997-10-0606 October 1997 Proposed Tech Specs Section 3.6 to Reflect Conversion to Improved STS ML20217G3781997-10-0606 October 1997 Proposed Tech Specs Section 3.7 Re Change Request to Convert to Improved STS ML20211J2751997-10-0202 October 1997 Proposed Tech Specs,Reflecting New Electrical Capacity for 1B Edg.Significant Hazards Considerations Associated W/Change Have Been Evaluated ML20217C7361997-09-29029 September 1997 Proposed Tech Specs Page Omitted from 970609 License Amend Request Re Conversion to Improved TSs ML20211J2981997-09-18018 September 1997 Pump & Valve IST Program Third Ten-Yr Interval for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20210T8701997-09-10010 September 1997 Proposed Tech Specs Rev 5 to Section 3.4 of Original License Amend Application & Other Changes Identified by Personnel ML20210K9711997-08-14014 August 1997 Proposed Tech Specs,Reflecting Removal of TSTF-115,as Well as Other Changes Identified by Plant Personnel ML20149H5821997-07-21021 July 1997 Rev 2 to TS Sections 4.0 & 5.0,converting to Improved Std Tss,Per NUREG-1432 ML20148P7171997-06-27027 June 1997 Proposed Tech Specs Revising Wording to Support Installation of Tube Sleeves as Alternative to Plugging to Repair Defective SG Tubes ML20141G4471997-06-16016 June 1997 Ccnpp Unit 2 Cycle 12 Startup Testing Rept ML20141D9341997-05-0909 May 1997 Radiation Safety Procedure 1-104, Area Posting & Barricading & High Radiation Area Pre-Entry Checklist ML20135F0441997-03-0606 March 1997 Proposed Tech Specs,Superceding Previously Submitted Marked Up Pp for ABB-CE Sleeves.New Info to Be Incorporated in Updated Licensing rept,CEN-630-P,Rev 01, Repair of 3/4 OD SG Tubes Using Leak Tight Sleeves ML20134E3221997-02-0303 February 1997 Proposed Tech Specs for Vol 16,Unit 1 Current Markup Improved Conversion License Amend Request ML20134E3361997-02-0303 February 1997 Proposed Tech Specs Vol 17,Unit 2 Current Markup Improved Conversion License Amend Request ML20134D3041997-01-31031 January 1997 Proposed Tech Specs Re Requirements to Allow Increased SG Tube Plugging ML20210P3971996-12-0404 December 1996 Rev 2 to RP-2-101, Administrative Procedure Radwaste Mgt ML20135A5231996-11-26026 November 1996 Proposed Tech Specs Adopting Option B of 10CFR50,App J to Require Types B & C Containment Leakage Rate Testing to Be Performed on performance-based Testing Schedule ML20134N1831996-11-20020 November 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML20210P3871996-10-17017 October 1996 Rev 2,Change 0 to Offsite Dose Calculation Manual ML20128Q8041996-10-14014 October 1996 Cycle 13 Summary of Startup Testing ML20128H6031996-10-0303 October 1996 Proposed Tech Specs,Changing Provisions for Receiving, Possessing & Using Byproduct,Source & Special Nuclear Matl at Plant ML20117L7991996-09-10010 September 1996 Proposed Tech Specs 3/4.3 Re instrumentation,3/4.5 Re ECCS & 3/4.6 Re Containment Sys ML20117L3441996-09-0404 September 1996 Proposed Tech Specs Clarifying License Amend Request Re Implementation of Changes to Radiological Effluent TSs as Proposed by GL 89-01 ML20116F8281996-08-0101 August 1996 Proposed Tech Specs Re Use of Blind Flanges in Place of Containment Purge Valves During Operation ML20116E3771996-07-26026 July 1996 Proposed Tech Specs Allowing Repair of Defective SG Tubes by Electrosleeving ML20117F6431996-05-15015 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls ML20101K6011996-03-28028 March 1996 Proposed TS Figure 3.1.1-1 Re Change to Moderator Temp Coefficient 1999-09-01
[Table view] Category:TEST REPORT
MONTHYEARML20195B2751999-03-31031 March 1999 Rev 0 to Rept 98-FSW-021, Corrosion Test of SG Tubes with Alloy 800 Mechanical Sleeves ML20195B2861998-06-0505 June 1998 Rev 0 to Rept 98-TR-FSW-005, Test Rept on Alloy 800 Mechanical Sleeve-Addl Qualification Testing Using Low Yield Strength Tubing ML20141G4471997-06-16016 June 1997 Ccnpp Unit 2 Cycle 12 Startup Testing Rept ML20128Q8041996-10-14014 October 1996 Cycle 13 Summary of Startup Testing ML20086E3111995-07-0505 July 1995 Ccnpp Unit 2 Cycle 11 Summary of Startup Testing ML20072J0951994-08-19019 August 1994 Ccnpp Unit 1 Cycle 12 Summary of Startup Testing ML20046D4081993-08-13013 August 1993 Cycle 10 Summary of Startup Testing. ML20118C0101992-07-31031 July 1992 Reactor Containment Bldg Integrated Leakage Rate Test Final Rept ML20082F6811991-08-13013 August 1991 Steam Generators 21 & 22 Eddy Current Testing Final Rept Apr-Jul 1989 ML20082F6831991-08-13013 August 1991 Steam Generators 21 & 22 Eddy Current Testing Final Rept Aug-Oct 1990 ML20082F4901991-08-0202 August 1991 Cycle 9 Startup Rept ML20024H6421991-01-31031 January 1991 Primary Reactor Containment Integrated Leakage Rate Test Final Rept ML20043C6031990-05-25025 May 1990 Startup Review Board Self-Assessment Rept:Apr 1990 Unit 1 Startup. ML20154S7281988-09-29029 September 1988 Steam Generators 11 & 12 Eddy Current Testing,Apr-Jun 1988, Final Rept ML20154D3441988-09-0909 September 1988 Summary of Startup Testing for Cycle 10 ML20235T9251988-06-30030 June 1988 Steam Generators 11 & 12 Eddy Current Testing Final Rept Apr/June 1988 ML20151Z6241988-05-31031 May 1988 Primary Reactor Containment Integrated Leakage Rate Test ML20235Y1051987-04-30030 April 1987 Steam Generator 21 & 22 Eddy Current Testing Final Rept, Mar/Apr 1987 ML20148T2861987-04-30030 April 1987 Steam Generator 21 & 22 Eddy Current Testing Final Rept ML20154L6701985-11-30030 November 1985 Primary Reactor Containment Integrated Leakage Rate Test Rept ML20133G4591985-10-0808 October 1985 Corrected Summary of Startup Testing for Cycle 8 ML20203K9721985-09-30030 September 1985 Reactor Vessel Matl Surveillance Program for Calvert Cliffs Unit 2 Analysis of 263 Degree Capsule, Final Rept ML20134E4321985-05-31031 May 1985 Primary Reactor Containment Integrated Leakage Rate Test Rept ML20094A1541984-10-0808 October 1984 Summary of Startup Testing for Cycle 6 ML20087K6091984-02-27027 February 1984 Summary of Startup Testing for Cycle 7 ML20024B6471983-07-0101 July 1983 Reactor Containment Bldg Integrated Leakage Rate Test Rept. W/830701 Ltr ML20073C8971983-03-24024 March 1983 Summary of Startup Testing for Cycle Five ML20071D7691982-12-31031 December 1982 Eddy Current Insp of Steam Generators 21 & 22, Final Rept ML20067E0041982-11-30030 November 1982 Integrated Leak Rate Test Rept ML20065D1021982-09-21021 September 1982 Yr Tendon Surveillance Rept, Vols 1 & 2 ML20027C5361982-08-31031 August 1982 Nonproprietary Version of Results of Eddy Current Testing on Guide Tubes at Calvert Cliffs I After Cycle 5. ML20071D7371982-05-31031 May 1982 Eddy Current Insp of Steam Generators 11 & 12, Final Rept ML20041A8201982-02-28028 February 1982 Fire Evaluation of Doors & Water Curtain. ML20003E8941981-04-0808 April 1981 Summary of Startup Testing for Fifth Cycle. ML19331E1631980-08-15015 August 1980 Fire Stop Penetration Tests on Fire Protection Sys, Final Rept Re Slab 2 ML19318A0841980-06-12012 June 1980 Summary of Startup Testing for Third Cycle. ML19296B0471980-02-0808 February 1980 RCS Asymmetric Loads Evaluation Program;Interim Rept. ML19296C7791979-11-16016 November 1979 Primary Reactor Containment Integrated Leakage Rate Test. ML19254D2981979-10-15015 October 1979 Summary of Startup Testing for Fourth Cycle. ML19269C7631979-02-0505 February 1979 Summary of Startup Testing for Cycle 2. ML20210T5001977-05-12012 May 1977 Startup Rept ML20210T4571975-08-29029 August 1975 Bg&E Calvert Cliffs Nuclear Power Plant Unit 1 Startup Test Rept 1999-03-31
[Table view] |
Text
BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT UNIT 2 Docket No. 50-318 License No. DPR-69
SUMMARY
OF STARTUP TESTING FOR CYCLE SIX 8411060291 841008 PDR ADOCK 05000318 P pyg
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SUMMARY
OF STARTUP TESTING FOR CALVERT CIJFFS UNIT TWO CYCLE SIX I. The following tests were conducted for the startup of Calvert Cliffs Unit Two Cycle Six. All tests were conducted in a manner similar to Initial Startup (Reference 1).
A. CEDM/CEA Performance Test B. RCS Flow Verification C. Initial Criticality D. CEA Symmetry Check -
E. Critical Boron Concentration Measurements F. IsothermalTemperature and Power Coefficient Measurements G. Group Rod Worth Measurements II. Power Distribution Measurements II. The results of these tests and comparison with predictions are as follows:
A. The proper functioning of the CEDMs and CEA position indication was verified through insertion and withdrawal of CEAs. All CEAs reached a 90% insertion in less than 3.1 seconds at hot, full flow conditions. The slowest CEA (56) reached 90% insertion in 2.54 seconds.
l B. Reactor Coolant Flow was verified to be consistent with previous testing.
C. Initial criticality was achieved at 1615 ppm Boron with CEA Group 5 at 87.7" withdrawn. Predicted value was 1576 ppm Boron.
D. The CEA Symmetry Check verified that all CEAs were attached to their extension shafts. An evaluation of the quantitative reactivity change for dual CEAs yielded an azimuthal tilt estimate of 2.75%, well within the 10% acceptance limit.
- E. Critical Boron Measurements - Table 1.
F. Isothermal Temperature and Powcr Coefficients - Table 2.
G. CEA Group Worth Measurements - Table 3. .
H. Power Distribution Measurements - Table 4, Figure 1 and 2.
III. All tests were within acceptance limits.
The ARO zero power Moderator Temperature Coefficient (MTC) was determined to be +.54 x 10-4 delta rho /0F. Although this was well within
- the acceptance criteria (t.3 of prediction), it exceeded the Technical 1
Specification limit of +.5 x 10-4 delta rho / F. Special test exception 3.10.2 was invoked until Low Power Testing was complete, at which time CEAs were inserted to reduce MTC. Operational restrictions were placed on boron concentration to ensure that MTC remained ,within limits during power
- escalation and early in the cycle until excess core reactivity was reduced.
l These actions were taken with concurrence from the fuel vendor and the Plant Safety Committee.
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TABLE 1 CRrrICAL BORON MEASUREMENTS Measured Predicted All Rods Out,5320F 1629 ppm 1590 t 50 ppm CEA Group's Inserted 5,4,3,2,1 1366 ppm 1336 t 50 ppm TABLE 2 ISOTHERMAL TEMPERATURE COEFFICIENTS AND POWER COEFFICIENTS ITC Measured Predicted Zero Power, CEA Group +.389 x 10-4 +0.30 t 0.3 x 10-4 5 at All Rods Out delta Rho / F delta Rho / F 50% Power, CEA Group .020 x 10-4 0.03 t 0.3 x 10-4 5 at 105" Withdrawn delta Rho / F delta Rho / F 100% Power, CEA Group -0.319 x 10-4 -0.27 t 0.3 x 10-4 5 at 105" Withdrawn delta Rho / F delta Rho /0F POWER COEFFICIENT 50% Power, CEA Group -1.012 x 10-4 -1.00 0.2 x 10-4 5 at 105" Withdrawn delta Rho /% Power delta Rho /% Power 100% Power, CEA Group -0.933 x 10-4 -0.88 t 0.2 x 10 -4 5 at 105" Withdrawn delta Rho /% Power delta Rho /% Power l
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I' TABLE 3 CEA GROUP WORTH MEASUREMENTS Measured Predicted
(% delta Rho) (% delta Rho)
Group 5 0.396 0.420 t .063 Group 4 0.215 0.233 i .035
. Group 3 0.585 0.615 i .092 Group 2 0.378 0.403 i .000 Group 1 0.700 0.754 i .113 TOTAL 2.274 2.425 i .242 TABLE 4 POWER DiffrRIBUTION MEASUREMENTS 50% Power 100% Power Acceptance Acceptance Measured Limits Measured Limits F gT 1.6804 1.785 1.5994 1.700 Ff 1.5972 1.720 1.5197 1.650 Tq 0.0109 0.030 0.0036 0.030 f
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ASSEMBLY RELATIVE POWER DENSITY FOR 50% POWER
,, UNIT 2 CYCLE 6
. PREDICTED: 50% POWER, EQUILIBRIUM XENON, BANK 5 @ 105 IN. WITHDRAWN, 40 M4D/T MEASURED: 47.4% POWER, EQUILIBRIUM XENON, BANK 5 @ 105 IN. WITHDRAWN, 34 MWD /T FIGURE 1 MEASURED HC 1 HO 2 FREDICTED O.73E2 C.9159
- 4 D 1 FF. 0.770C 1.0400 Y
-4.13 -11.64 OIFF.= MEASURED-PREDICTED X100 PREDICTED HC 3 HC 4 H0 $ F0 '6I CO 7 0.6342 1.1106 1.196E 0.5444 1.0967 0.E300 1.1300 1.21C0 0.E700 1.1000 x
- 0. 51 -1.72 -1.09 -2.94 -0.30 .
HD 8 CO 9 C1 10 C0 11 El 12 C1 13 0.8863 1.1795 1.1154 1.011C 0.6667 0.6447 0.9100 1.1700 1.1300 1.0100 0.6700 0.8400 W
-2.60 C. B1 -1.20 0.10 -0.19 0. 56 H0 14 CO 15 C1 16 CO 17 F0 18 H1 19 El 20 0.B863 1.1503 1.1359 1.2512 0.8749 1.1947 0.7460 0.9100 1.1700 1.1600 1.2400 0.6800 1.1800 0.7300 V
-2.60 -1.68 -2.06 0.90 -0.58 1.25 2.19 HO 21 00 22 C1 23 C0 24 D1 25 C0 26 F0 27 CO 26 0.8342 1.1795 1.1359 1.2123 0.7799 1.0939 0.9696 1.2218 0.8300 1.1700 1.1600 1.1900 0.8000 1.0000 0.9600 1.1700 T
- 0. 51 0.81 -2.06 1.87 -2.53 1.29 1.02 4.43 HC 29 C1 30 C0 31 D1 32 H1 33 FC 34 'H 1 35 D1 36 1.1106 1.1154 1.2512 0.7796 1.2236 0.9033 1.2723 0.8047 1.1100 1.1200 1.2300 0.8000 1.2400 0.9100 1.2700 0 E100 S 0.05 -0.41 1.72 -2.53 -1.31 -0.74 0.15 -0.65 HC 37 C1 3B FO 39 CO 40 FO 41 00 42 FC 43 GC 44 1.1968 1.0110 0.5749 1.0939 0.9023 1.1E37 0.9069 1.0775 HC 45 1.1600 0.9900 0.EE00 1.0500 0.9100 1.1e00 0.E900 1.04C0 R 0.7382 1.42 2.12 -0.5E 1. 29 -0.74 2.04 1.90 3.61
- 0.7300 1.12 FC 46 El 47 H1 4E FO 49 HI 50 r0 51 H2 52 O! 53 0.6444 0.66E7 1,1947 0 C695 1.2723 0.C0c4 1.1325 0:c512 WO 54 0.E200 0.e50C 1.1700 0.9500 1.2300 0.EE00 1 .100 0 65C0 N C.9189 2.96 2.88 2.11 2. 0E -0.60 3. 06 2.57 0. 16 M 0.9700
-5 27 C0 55 C1 56 D1 57 GO SE D1 59 CO 60 21 61 30 e2 1.0967 0.6447 C.7460 1.2216 0.E047 1 0775 0.6512 0.5673 1.1000 0.6400 0.7300 1.1700 0.E100 1.0400 0.6500 0.5600 L
-0.30 0.56 2. 1 C 4.43 -0.c5 3. e1 0.1 E 1.30 1 2 3 4 5 6 7 9 11 E 10 l
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.- 3
, I r ASSEMBLY RELATIVE POWER, DENSITY FOR 100% POWER UNIT 2 CYCLE 6
. PREDICTED: 100% POWER, EQUILIBRIUM XENON, BANK 5 0105. IN. , WITHDRAWN, 250 MWD /T '
MEASURED: 97.0% POWER, EQUILIBRIUM XENON, BANK 5 @ 105 IN.- WITHDRAWN, 302.4 MWD /T FIGURE 2*->
q H0 1 H0 .' 2
~
O.7135 0.862E 0.7300 0.9700 Y 11 O I ~F. -E.99
-2.26 014. = MEASURED-PREDICTED X100 4 HO 5 FO 6 .CO 7 PREDICTED HQ -- 3 ' HC 0.7951 1.0644 1.1414 0.8229 1.0714 0.0000 1.0700 1.1500 0.8400 1.0600 1.06 X
-0.61 -0.52 -0.75 -2.04 H0 2 CO 9 C1 10 CO 11 El 12 C1 13
, O.951E 1.1393 1.0321 0.9973 0.6924 0.8559 0.6900* 0.6600 W 0.8800 1.130C: 1.1100 1.0100
-0.48
-3.20 0. S2 -7.02 -1.26 C. c HO 14 CO 15 C1 16 CO 17 F0 18 H1 19 El 20 0.9519 1.1135 1.1128 1.2444 C.8663 1.2220 C.7641 0.9800' 1.1400 1.1500 1.2300 C.9000 1.1900 2.60 C.7600 C. 54 V
-3.20 -2.32 -3.23 1.17 -1.52 HD 21 CO~ 22 C1 23 CO 24 D1 25 CO 26 F0 27 CO 20 0.7951 1.1393 1.112e 1.1995 0.e067 1.1215 0.9934 1.2552 0.7900 1.1300 1.1500 1.1900 0. S.~.00 1.1000 0.9900 1.2000 T O.65 O.82 -3.23 C. 90 -1J62 1.95 0.34 4.60 H0 29 C1 30 C0 31 D1 32 HI 33 FO 34 H1 35 D1 36 1.0644 1.0321 1.24A4 0.5067 1.2634 0.9323 1.3071 C.S3EE 1.0600 1.1000 1.2300 0.E300 1.2600 0.27 0.9400
-0.82 1.3000 0.55 0.6400
-0.14 5
0.42 -6.17 1. 17 -2.51 e
HQ 37 C1 36 FC 39 GC 40 FC 41 CO 42 FO 43 C0 44 1.2220 0.9376 1.1257 1.1414 0.9973 0.EC63 1.1215 0.c323 0.*300 1.0500 R Ho 45 1.1300 0.9900 0.e000 1.1000 0.9500 1.2000 1. E0 0.82 4.23 C.7135 1.01 0.74 -1.52 1,95 -1. E 6 5 C.7000
- 1. c3 FC 46 El 47 H1 4E FCC.*c34 4' H 50 FC 51 H1 52 31 53 0.E229 0. c 24 1.2220e 1.0071 0.e376 : :eE7 0.7535 Ho 54 0.S100 0.6700 1.1c00 0.9500 1.3100 0.9200 1.1600 0.e900 N 3.34 2. e4 1.37 -0.22 1.91 3.34 1.96 0.8E29 1.59
-4.04 CO 55 C1 56 D1 57 GO SE D1 59 CG 60 Di 61 DC 62 1.C714 0.9559 0.7e41 1.2552 0.SOEE 1.1257 0.7035 0.6133 1.0600 0.0600 0.7e00 1.2000 0.E400 1.0800 0.6900 0.6100 L 4.6C -0.14 4. 23 1. c 6 C. 54
- i. DE -0.48 0. 54
.) 7 9 11 1 2 3 4 5 6 E 10 r
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REFERENCES
- 1. Calvert Cliffs Nuclear Power Plant Unit 2 Startup Test Report, May 12,1977.
l
- l. e e.p BALTIM ORE GAS AND ELECTRIC CHARLES CENTER.P.O. BOX 1475 BALTIMORE, MARYLAND 21203 l
ARTHum E. LUNOVALL, JR.
vice Parsiocur.
SuppLv October 8,1984 Dr. Thomas E. Murley Regional Administrator U.S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No. 2, l Docket No. 50-318 Report of Startup Testing for Cycle 6 l
Gentlemen:
j Startup testing for Calvert Cliffs Unit 2, Cycle 6 was completed on July 23,1984. A summary of the results from those tests is enclosed.
Very,truly yours,
]
s'
-( m _l ne~
AEL/JFW/jes Enclosure ec: Director Inspection and Enforcement U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 R.A. Clark D.A. Brune, Esq.
G.F. Trowbridge, Esq.
D.H. Jaffe, NRC R.R. Mills, CE T. Foley, NRC N
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