Letter Sequence Other |
|---|
TAC:46174, (Closed, Approved) TAC:7317, (Closed, Approved) TAC:7321, (Closed, Approved) TAC:7420, (Closed, Approved) TAC:7546, (Closed, Approved) TAC:8169, (Closed, Approved) TAC:8631, (Closed, Approved) |
Results
Other: ML19207C172, ML19209B403, ML19256A848, ML19259A812, ML19263B926, ML19270G086, ML19273B549, ML19274D206, ML19276E491, ML19276F808, ML19281A096, ML19282C563, ML19282C601, ML19282C615, ML19289F472, ML19317H313, ML20037A204, ML20037A229, ML20049A130, ML20062G381, ML20062G387, ML20064C234, ML20064D492, ML20064E453, ML20064H429, ML20076A802, ML20076A836, ML20076A843, ML20076A904, ML20076A952, ML20076B087, ML20076B088, ML20076B089, ML20244A548, ML20244A585
|
MONTHYEARML20236C3041976-09-14014 September 1976
Notification of 760928 Meeting W/Util in Bethesda,Md to Discuss Util Concepts for Proposed Neutron Shield for Plant. Summary of Neutron Streaming Problem Encl
Project stage: Meeting
ML20207B6331977-11-0909 November 1977
Requests Determination If Throttle Valves Are Used to Obtain Required Flow Distribution in HPSI or LPSI Sys.If Throttle Valves Used,Tech Specs Should Be Changed within 60 Days to Incorporate Encl Surveillance Requirements
Project stage: Other
ML19329C3691977-11-18018 November 1977
Requests Info Re Throttle Valves Used to Obtain Required Flow Distribution in High Pressure & Low Pressure Safety Injection Sys.If Throttle Valves Are Used,Tech Specs Should Reflect Change.Sample Surveillance Tech Specs Encl
Project stage: Other
ML20214S8231977-12-16016 December 1977
Application for Amend to License DPR-65,revising Tech Specs Page 3/4 5-5 to Increase Min Requirement for Trisodium Phosphate Dodecahydrate in Item 4.5.2.c.3
Project stage: Request
ML20214S8271977-12-31031 December 1977
Proposed Tech Specs Pages 3/4 5-5,increasing Min Requirement for Trisodium Phosphate Dodecahydrate in Item 4.5.2.c.3
Project stage: Other
ML20207B6351978-04-28028 April 1978
Discusses Listed Action Taken to Close Issue Re Necessary Tech Spec Changes to PWR Licenses to Incorporate Hpsi/Lpsi Sys Throttle Valves Surveillance Requirements.List of PWR Plants & Sample Generic SER Encl
Project stage: Other
ML19344A8901978-07-31031 July 1978
Forwards Addl Info Re Control of Heavy Loads Near Spent Fuel,Proposed Neutron Shield Design & Withdrawal of Applicants Tech Spec Proposed Change Re Revision to Containment Leak Rate Testing
Project stage: Withdrawal
ML20244A4781978-09-12012 September 1978
Responds to 780821 NRC Ltr Re Violation Noted in Inspec Rept 50-366/78-26.Does Not Consider Item to Be a Noncompliance. Corrective Action:Slight Setpoint Adjustment of Refueling Water-Low Instru Channels.(Encl to 7810060211)
Project stage: Other
ML20064C2341978-10-11011 October 1978
Forwards Proposed Tech Specs to Require Diesel Generator Start Time of Less than or Equal to 20
Project stage: Other
05000336/LER-1978-024-03, /03L-0 on 781004:during Surveillance Testing, Setpoint for Reactor Protec Sys Reactor Coolant Low Flow Trip on Channel B Was Out of Spec.Setpoint Was Readjusted. Rev Will Req Low Flow Trip Unit Setpoint Be Reset1978-11-0101 November 1978
/03L-0 on 781004:during Surveillance Testing, Setpoint for Reactor Protec Sys Reactor Coolant Low Flow Trip on Channel B Was Out of Spec.Setpoint Was Readjusted. Rev Will Req Low Flow Trip Unit Setpoint Be Reset
Project stage: Request
ML20064D4921978-11-0101 November 1978
Presents Details of Stretch Power Effort in Advance of Execution to Enable Facility to Operate at 2,700 Mwt Following Second Refueling Outage
Project stage: Other
ML20049A1301978-11-13013 November 1978
Forwards Nuc Shield Design as Alternate to That Proposed in .Design Incorp ALARA Considerations & Philosophy. Requests Expeditious Review to Allow Target Installation Date.Oversize Drawing Available in Central File
Project stage: Other
ML20027A4181978-11-15015 November 1978
Notification of 781121 Meeting W/Ne Nuc Energy Co to Discuss Tech Review Effort & Schedule Necessary to Authorize Stretch Pwr Level Rating of 2700MWT
Project stage: Meeting
ML20064E4531978-11-18018 November 1978
Forwards Sys Description for Reactor Coolant Pump Shaft Speed Trip Function Being Installed by Util to Replace Steam Generator Differential Pressure Sys.Believes Proposal Is Exempt from Amend Fee
Project stage: Other
ML20062G3871978-12-14014 December 1978
Sleeved Guide Tube Inspec Prog, CEN-104(N)-NP.Describes Inspec Prog to Show Performance Re Wear.Edited to Delete Info W/Held from Pub Disclosure IAW 10CFR2.790
Project stage: Other
ML20064H4291978-12-15015 December 1978
Appl to Amend Oper Lic DPR-65 by Increasing Maximum Allowable Thermal Output of Subj Facil Over 2700MWt to Commence W/Cycle 3 on 790515.W/att Environ Impact Appraisal, Eval of Radiological Consequences & Site Meteorology
Project stage: Other
ML20062G3811978-12-18018 December 1978
Forwards non-proprietary Version of Sleeved CEA Guide Tube Inspec Prog,CEN-104(N)-NP,relating to Amend 38 to DPR-65. IAW 10CFR2.790.W/encl Affidavit
Project stage: Other
ML19256A5231978-12-21021 December 1978
Summary of 781221 Meeting Re Neutron Shield Design.Applicant Will Forward Qualifications of Design by mid-January 1979 & Request a Safety Evaluation by 790331
Project stage: Approval
ML19267A2841978-12-28028 December 1978
Requests Acceptance of Proposed Changes to Tech Specs for License DPR-65 Adding Requirement of Operable Charging Pump & Operable Flow Path as ECCS Subsys.W/Att Description of Proposed Changes
Project stage: Request
ML19274D2061978-12-29029 December 1978
Pursuant to 781215 Request by Applicant to Increase Thermal Power of Unit to 2700 Mwt,Or Requests IE Evaluation of Utils Past Mgt & Discussion of Outstanding Insp Items Re Safe Operation at Stretch Power Level
Project stage: Other
ML19274D2521979-01-0303 January 1979
Summary of Meeting on 781121 in Bethesda,Md to Discuss Stretch Power Program Including Control Element Assembly Guide Tube Wear Basis,Cycle 2 & 3 Assemblies,Eccs, & Low Flow Trip.W/Tentative Review Schedule & Submittal Schedule
Project stage: Meeting
ML19259A8121979-01-0808 January 1979
Ack Receipt of 781101,781108 & 781215 Requests for Review & Comments on Stretch Power,Core Reload & Reactor Coolant Pump Speed Sensing Sys.Staff Considers Requests as First Submittals for Amend & Are Subj to Class V Fee
Project stage: Other
ML19256A8481979-01-0909 January 1979
Discusses Status of Proposed Tech Spec Revision Increasing Response Time of Encl Bldg Filtration Sys.Disagrees W/Nrc Dose Calculations.Contends 151 Rems Thyroid Dose & 3.8 Rems Whole Body Does Are Conservative
Project stage: Other
ML19263B9261979-01-17017 January 1979
Forwards $25,800 Payment for Licensing Fee Per NRC
Project stage: Other
ML19269C8461979-02-0606 February 1979
Responds to NRC Verbal Request for Addl Info on Proposed Mod to Tech Specs Re ECCS Performance Calculations for Charging Pump Flow.No Plant Mod Is Necessary & There Is No Change in Valve Motion or Operability Requirements
Project stage: Request
ML19263C4881979-02-12012 February 1979
Proposes Amend to License DRR-65.Proposed Changes Include Core Performance Characteristics & Safety Analyses Re Operation at 2,700 Mwt
Project stage: Request
ML19283B6651979-02-23023 February 1979
Forwards Rept on Neutron Shield Design Qualification. NRC Concerns Raised During 781128 Meeting Are Addressed in Rept. Items on Shield Movement,Leakage & Pressure Relief Valves Discussed in Forwarding Ltr
Project stage: Meeting
ML19281A0961979-02-27027 February 1979
Supports Proposed License Amend to Increase Rated Thermal Power to 2,700 Mwt,Starting W/Cycle 3 Operation.Forwards Addl Info Re Control Rod Ejection,Main Steam Line Rupture & Seized Rotor Event
Project stage: Other
ML19276E4911979-03-0202 March 1979
Forwards Proposed Amend to License DPR-65,changing Tech Specs to Incorporate Reactor Coolant Pump Speed Sensing Sys. W/Affidavit & Oversized Drawing
Project stage: Other
ML19276F5721979-03-14014 March 1979
Request for Addl Info Re Utils Cycle 3 Reload/Stretch Power Request of 790212
Project stage: RAI
ML19282C6011979-03-22022 March 1979
Forwards Results of non-LOCA Safety Analysis Necessary to Support Cycle 3 Operation at 2,700 Mwt
Project stage: Other
ML20244A5481979-03-23023 March 1979
Provides Trip Setpoint for Proposed Tech Spec Revision to Incorporate Reactor Coolant Pump Speed Sensing Sys as Addition to Reactor Protection Sys
Project stage: Other
ML19282C5631979-03-23023 March 1979
Util Determined Certain stem-mounted Limit Switches on safety-related Valves May Not Be Suitable for Svc in LOCA Containment.Forwards List of Specific Switch Types & Valves on Which Switches Are Installed
Project stage: Other
ML19273B5681979-03-27027 March 1979
Responds to NRC 790314 Request for Addl Info Re Cycle 3 Operation
Project stage: Request
ML19282C6151979-03-28028 March 1979
Forwards Info Requested in .Desribes Loop Current Step Response Method of in Situ Response Time Testing of Resistance Temperature Detectors
Project stage: Other
ML20037A2041979-03-29029 March 1979
Forwards Proposed Insp Program for Sleeved Guide Tubes. Program Withheld (Ref 10CFR2.790)
Project stage: Other
ML19273B5491979-03-30030 March 1979
Forwards Results of Large Break Loca/Eccs Performance Analysis.Qa Verification by C-E,NSSS & Fuel Supplier Is Expected on 790410.W/basis for no-fee Determination
Project stage: Other
ML20076A8021979-04-0606 April 1979
In Answer to IE Bulletin 79-01,environmentally Qualified stem-mounted Limit Switches W/Appropriate Documentation Can Be Procured.Util Will Replace Switches W/Qualified Switches Prior to Start of Cycle 3 Operation Scheduled for May 1979
Project stage: Other
ML19276F8081979-04-0909 April 1979
Advises That QA Verification of Small & Large Break Loca/Eccs Performance Analysis Has Been Completed.Ltrs to NRC & 790330 Are Sufficient to Show Compliance w/10CFR50.46 Criteria
Project stage: Other
ML20244A5851979-04-12012 April 1979
Forwards Info Re Proposed Revisions to Tech Specs to Reflect Installation of Reactor Coolant Pump Speed Sensing Sys to Provide Protection for 4-pump Loss of Flow Event
Project stage: Other
ML20076A8361979-04-13013 April 1979
Eddy Current Test Has Been Performed.No Tube Defects Discovered & No Corrective Action Based on Tube Defects Required.Preliminary Analysis of Results of Insp Indicates Denting Rate Has Been Reduced
Project stage: Other
ML20076A8431979-04-13013 April 1979
Steam Generator Insp
Project stage: Other
ML20076A9041979-04-18018 April 1979
Responds to IE Bulletin 79-01.One Solenoid Installed on safety-related Valve in Plant Containment Has Not Been Qualified for Svc in LOCA Environ.Solenoid Will Be Replaced Before Start of Cycle 3 Operation
Project stage: Other
ML19270G0861979-04-24024 April 1979
Responds to IE Bulletin 79-07 Re Seismic Stress Analyses of safety-related Piping
Project stage: Other
ML20076A9551979-04-26026 April 1979
Responds to NRC 780419 Request for Insulation Resistance Tests.Forwards Electrical Penetration Testing Evaluation. Modified Conductor Configuration Is Acceptable for Cycle 3 Operation
Project stage: Request
ML20076A9521979-04-26026 April 1979
Discusses Guide Tube Insp Program.Pull Tests Performed on 35 Sleeves.Evaluation of Data Indicates Sleeves Are Functioning as Expected
Project stage: Other
ML19289F4721979-04-30030 April 1979
Responds to IE Bulletin 79-04, Incorrect Weights for Swing Check Valves Mfg by Velan Engineering Corp. Lists Subj Valves Used in Seismic Category I Piping Sys.Investigation Indicates No Drawing Discrepancies Re Valves
Project stage: Other
ML20037A2291979-05-0202 May 1979
Response to NRC Question 2.2 on Cycle 3 Safety Analysis, Nonproprietary Version
Project stage: Other
ML20244A6131979-05-0303 May 1979
Forwards Responses to Request for Addl Info Re Cycle 3 Safety Analysis.Nonproprietary Rept Encl.Proprietary Version Withheld (Ref 10CFR2.790)
Project stage: Request
ML20037A2281979-05-0303 May 1979
Forwards Responses to Request for Addl Info Re Cycle 3 Safety Analysis.Nonproprietary Rept Encl.Proprietary Version Withheld (Ref 10CFR2.790)
Project stage: Request
1979-01-09
[Table View] |
Text
.
IMHtTHI!JWI' ITI'II.ITIIES 3
- 1.5A. IT L~~
N0ro*nE CONNECTICUT 06t01
- '.,::,: ;;;=: -
- amww, L
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October 11, 1978 Docket No. 50-336 Director of Nuclear Reactor Regulation Attn: Mr. R. Reid, Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C.
20555
References:
(1)
W. G. Counsil letter to R. Reid dated August 11, 1978.
(2)
D. C. Switzer letter to G. Lear dated December 13, 1977.
(3)
D. C. Switzer letter to R. Reid dated February 23, 1978.
Gentlemen:
Millstone Nuclear Power Statloc, Unit No. 2 Diesel Generator Start Times In Reference (1), at the request of the NRC Staff, Northeast Nuclear Energy Company (NNECO) proposed to modify Technical Specification 4.8.1.1.2.a.3 to require a diesel generator start time of less than or equal to 20 seconds. The appropriate-ness of the 20-second specification is discussed in References (2) and (3).
During the past several weeks, discussions with the NRC Staf f have identified the need for additional information to clarify the acceptability of the proposed interval;.the Staff has also requested additional peripheral information regarding diesel generator performance. Accordingly, the following information is provided.
It is emphasized that although 20 seconds is an acceptable interval from the perspective of fulfilling safety analysis assumptions and is, therefore, the appropriate value for Technical Specifications, diesel generator start times in excess of 12 seconds will be cause to initiate investigation and the appropriate corrective action will be taken. The diesel generators were designed to start within 12 seconds and this feature remains unchanged. Nonetheless, it is not appropriate to specify a start time less than 20 seconds because it is not re-quired by docketel safety analyses.
During recent discussions with the Staff, additional information was also requested regarding all equipment powered by the diesel generators under loss of offsite power conditions. Accordingly, Attachment 1 is provided and addresses the permanently connected loads and each sequence step. A 20-second start time is substantiated.
The Staff had also requested that data regarding documented diesel generator starting times be provided. Accordingly, Attachment 2 provides a tabulation of starting times for both diesel generators. Included are the date of the sur-veillance, the start time in seconds, and, where retrievable, a brief description
'7f/0(7 o JL/ 0 f
4
. of deficiencies associated with the diesel generators for those instances when 12 seconds was exceeded.
Note that for those instances where "> 12 seconds" is listed, it should not be inferred that 20 seconds was exceeded. In those instances, if the diesel failed to start within 12 seconds, the start signal was automatically interrupted for equipment protective purposes.
We trust the above information is sufficient to allow the NRC Staff to affirma-tively disposition all license amendment requests associated with the Engineered Safety Features.
Very +ruly yours, NORTHEAST NUCLEAR ENERGY COMPANY J
ll/s. xawa-W. G. Counsil Vice President Attachments i
l l
l
4 DOCKET NO. 50-336 ATTACRMENT 1 DIESEL GENERATOR LOADING OCTOBER, 1978
The purpose of the following discussion is to substantiate the acceptability of a 20-second start time for the diesel generators, recognizing that the original design calls for a 12-second start time.
It is important to recognize that the associated delay in actuation of Engineered Safety Feature equipment is due ex-clusively to delays in diesel starting, rather than delays or changes in sequencing steps. In other words, sequence step 1 still occurs two (2) seconds following breaker closure, sequence step 2 still occurs six (6) seconds af ter step 1, etc.
A.
Permanently Connected Loads (1) Emergency lighting (2) Instruments (3) Battery Charger (4) MOV's (5) Load Center Losses (6) Diesel Air Compressers (7) Service Water Strainer (8) Boric Acid Tank Heaters (9) Boric Acid Heat Tracing (10) 02 Analyzer Exchanger The above items identify the larger components associated with Engineered Safety Feature equipments. Demonstration of the acceptability of these larger components substantiates the acceptability of a 20-second delay time for the permanently connected loads. These loads are immediately re-energized upon diesel generator breaker closure onto its emergency bus and all are capable of withstanding a 20-second interruption delay without compromising their safety function. For example, MOV's need not be moved prior to HPSI or LPSI pumpa delivering flow. A 20-second delay for operation of the battery charger is of no consequence as the batteries alone will support electrical requirements.
B.
Sequence Step 1,1.5 - 2.2 seconds after diesel start (1) NOV's - As stated before the valves need not be moved prior to SI pump operation.
(2) [arvice Water Pump - This pump provides cooling water to the RBCCW heat exchangers, and other auxiliary systems. A delay in diesel starting to 20 seconds is not detrimental to these systems. Relative to each other, all components involved are being energized at the same time as in the 12-second start time case.
(3) HPSI Pump - See Reference (2).
(4) Containment Air Recirculation Fans - As stated in response to Question 14.12.1 of the Millstone Unit No. 2 FSAR, Amendment 39, the CAR fans are assumed available 32 seconds following the rupture. The accepta-bility of a 20-second diesel start time is demonstrated as follows.
,e..-
- n. - - - - - -n--,--.---------m,---------
,--,,.----w a-
Time, Seconds Action 0
Rupture 1
SIAS Signal 21 Diesel Breaker Closes 23.2 Sequencer starts CAR fans (includes maximum allowable sequencer tolerance) 28.2 Fans performing design function (assuming 75% of rated voltage available)
Note that the above sequence is only applicable to the single CAR fan tha t is not operating at the time of the incident. The other three CAR fans are operating during nrrmal operation. Assuming a loss of offsite power, these three fans will begin to coast down from the normal operating speed of 1800 RPM.
Power will be returned to the fans 23.2 seconds and fan speed will stabilize at the low speed, i.e., accident speed of 900 RPM.
This speed will be attained prior to the 28.2 seconds described above.
C.
Sequence Step 2, 7.0 - 8.4 seconds af ter diesel start (1) RBCCW Pump - The rationale presented in item B.2, Service Water Pump, is applicable in this instance.
(2) Charging Pumps - No credit is taken in any safety analysis.
(3) Boric Acid Pumps - No credit is taken in any safety analysis.
D.
Sequence Step 3, 12.5 - 14.6 seconds af ter diesel start (1) LPSI Pump - See Reference (2).
(2) Containment Sprav Pump - See Reference (2).
s')
Enclosure Building Filtration Fan - See Reference (3).
E.
Sequence Step 4, 18.0 - 20.8 seconds after diesel start (1) Diesel Generator Vent Fan - An additional eight (8) second delay in energization of this component will not adversely affect diesel genera-tor performance.
(2) HVAC - No adverse affects for an additional eight (8) second delay.
DOCKET NO. 50-336 AITACHMENT 2 DIESEL GENERATOR START TIMES 1:
i t
l OCTOBER, 1978
i i'
s j
"A" DC START TIMES 1976 3/12/76 9
8/23/76
>12(4) 10/27/76 9
4/28/76 8
8/25/76 8.1 11/03/76 9
5/19/76 9
9/01/76 8
11/24/76 9.1 1
6/02/76 19(1) 9/01/76 8
12/01/76 9
4 6/23/76 8
9/10/76 8.3 12/09/76.
8-6/25/70 8.9 9/15/76 9
12/10/76 8
i 7/02/76 8
9/20/76 9
12/16/76 9
i 7/16/76 9
9/22/76 11 12/17/76 9
7/16/76
>12(2) 9/23/76 10 12/17/76 9
8/10/76
>12 (3) 9/29/76 8
12/18/76 8
l 8/13/76 10 10/06/76 8.8 12/18/76 8.2 j
8/16/76
>12(4) 10/06/76 8.7 12/19/76 9
8/17/76
>12 (4) 10/13/76 9
12/19/76 9
8/18/76 8.8 10/14/76 8.5 12/19/76 9
8/19/76 9
10/20/76 8
12/20/76 9.2 (1) Not available.
(2) Speed switch failure.
1 (3) Deenergization of RSST. Diesel starts and af ter securing it, attempted
- l to restart due to emergency start signal prasent. Governor was in "no
~
[
j fuel" position. Did not start within 12 sec.
(4) Faulty fuel oil booster servomotor.
I
"A" DG START TIMES 1977 1/10/77 9
5/04/77 7.8 9/28/77 9
1/10/77 8
5/04/77 8.9 9/29/77 8.7 1/21/77 9.2 6/02/77 8
9/30/77 - 'll
^
1/25/77 8
6/29/77 9.2 10/01/77 8.5 2/02/77 8.9 6/30/77 9
10/01/77 9
2/02/77 8
7/06/77 9
10/04/77 8
2/03/77 10 7/13/77 7.8 10/06/77 9
2/03/77 8
7/20/77 9
10/11/77 8.25 2/09/77 9
7/27/77 8.6 10/11/77 8.4 2/10/77 8
8/03/77 9
10/20/77 8.4 2/16/77 8.8 8/10/77 8.5 10/26/77 8
2/16/77 9
8/17/77 8
11/01/77 8.2 2/23/77 8.8 8/23/77 9
11/08/77 9
3/02/77 10 8/27/77 8.5 11/09/77 9
3/09/77 9.4 8/28/77 8.5 11/15/77 S.5 3/16/77 8.5 8/30/77 9.2 11/28/77 8.4 3/23/77 9
9/06/77 9.2 12/06/77 9
3/30/77 8.8 9/13/77 9
4/06/77 9
9/20/77 8.8 4/13/77 8.3 9/21/77 8.4 4/20/77 8.6 9/27/77 9
4/27/77 9
9/28/77 9
"A" DG START TIMES 1978 2/23/78 8.5 6/06/78 8.4 2/24/78 8.5 6/14/78 9
3/10/78 9.5 6/20/78 9
3/22/78 8.5 6/27/78 9
2/28/78 8.3 7/05/78 9
4/07/78 8.6 7/11/78 9
4/13/78 8.7 7/13/78 9
4/26/78 8
7/26/78 9
5/03/78 9
7/27/78 9
5/03/78 9
7/28/78 9
5/05/78 9
8/03/78 9
5/06/78 9.8 8 /03/78.
9 5/07/78 8
8/08/78 8.2 5/ 08 /78 9
8/09/78 9
l 5/08/78 8
8/15/78 8
5/10/78 9
8/29/78 8
5/11/78 8
9/05/78 9
5/17/78 8.4 9/16/78 8.5 l
5/18/78 8.5 9/12/78 10 5/24/78 8
9/19/78 8
L 5/31/78 8.6 10/03/78 9
9 "B" DG START TIMES 1976 3/11/76 8.5 8/17/76 12 10/14/76 9
3/12/76 8.8 8/18/76 8
10j27/76 8
3/16/76 8.5 8/18/76 9.0
~_ -
10/27/76 8
4/15/76 8
8/23/76 11
-11/03/76 8
,y,
, y:.
6/03/76 10
'8/24/76 8.5 I '+
11/04/76 9
6/16/76 9.3 8/24/76 8.8 11/10/76 8
6/23/76 8.2 8/25/76 8.9 11/13/76 9
6/24/76 8
9/03/76 8
11/19/76 9
6/25/76 8
9/10/76 8
11/24/76 9
7/14/76 9
9/17/76 8
12/01/76 8.6 7/16/76 11.5 9/22/7t, 10 12/08/76 8.7 7/21/76 8
.9/23/76 10 12/09/76 9.2 7/27/76 9.5 9/28/76 7
12/09/76 8.8 8/13/76 8.7 10/06/76 9
12/17/76 9
8/17/76 8.8 10/13/76 8
12/17/76 9
j 12/18/76 9
4
=
~
"B" DG START TIMES 1977 1/05/77 8
6/08/77 9.6 9/13/77 9
1/11/77 8
6/17/77 8.5 9/20/77 9
1/20/77 9
6/24/77 8.2 9/20/77 9
1/25/77 8
6/29/77 9
9/21/77 8.2 2/09/77 9
7/06/77 9
9/22/77 8.4 2/10/77 9
7/13/77 9
9/23/77 8.4 2/16/77 9
7/20/77 9
9/28/77 9
2/23/77 9
7/27/77 8.8 10/04/77 8.5 3/02/77 8
8/03/77 9.2 10/06/77 8.8
{
3/09/77 9.2 8/10/77 9
10/13/77 9
3/ 09/77 8.4 8/17/77 9
10/11/77 9.6 3/16/77 8.8 8/17/77 9
10/18/77 8.9 3/23/77 9
8/23/77 9
10/25/77 9
3/30/77 9
8/26/77 9
11/01/77 8.9 4/06/77 9
8/27/77 8.5 11/09/77 8.6 4/13/77 9
8/27/77 9
11/15/77 9.1 4/20/77 9
8/27/77 8.6 11/17/77 9
4/27/77 8.5 8/28/77 9
12/13/77 9.2 5/04/77 8.5 8/29/77 8.5 12/26/77 9
5/16/77 8
8/30/77 8.7 l
5/31/77 9
9/06/77
'8.9 i
J
.r
.e,.
g,
1 t
2 j
"B" START TIMES 1978 1/18/78 8
5/08/78 8
7/11/78 8.5
~
2/19/78 9
5/10/78 9.4 7/13/78 9
L -
t' 2/28/78 9
5/18/78 9
7/18/78 9
b-3/10/78 8
5/25/78 9
7/25/78 9
3/15/78 11 5/31/78 9.5 8/03/78 9
3/16/78 9
6/06/78 9
8/03/78 9
3/29/78 8.9 6/14/78 10 8/08/78 9.9 j
4/14/78 9.0 6/20/78 9
8/15/78 8.6 4/19/78 8.8 6/27/78 9
8/22/78 9
5/03/78 9
7/06/78 8.7 8/29/78 8.5 9/05/78 9
9/06/78 9
3 9/12/78 8.5 i
9/19/78 9
9/26/78 9
4 k
l T
4 yr -
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