|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20217P8041998-04-0707 April 1998 11RFO OTSG ECT Insp Scope ML20196B8771996-12-16016 December 1996 First Amended & Restated Master Decommissioning Trust Agreement Dtd as of 961231 Between Toledo Edison Co & Mellon Bank ML20196B8951996-12-16016 December 1996 First Amended & Restated Master Decommissioning Trust Agreement Dtd as of 961216 Between Cleveland Electric Illuminating Co & Mellon Bank ML20134D7821996-05-0808 May 1996 Rev 1 to Instrument Drift Data Analysis Methodology & Assumptions ML20091S4311995-08-31031 August 1995 USI A-46 Seismic Evaluation Rept. W/61 Oversize Drawings ML20138J1411994-02-28028 February 1994 Rev 0 to IPEEE,A-46 & Design In-Structure Response Spectra for Selected Bldgs at Dbnps ML20067D3311993-08-31031 August 1993 Technical Evaluation Rept,Evaluation of B&Wog Pressurizer Surge Line Thermal Stratification Program to Address NRC Bulletin 88-11 ML20091P5721991-10-31031 October 1991 Reactor Containment Bldg Integrated Leak Rate Test Including,Type A,B & C Periodic Test Results ML20070Q1911991-03-25025 March 1991 NRC Form 474 Simulation Facility Certification ML20058L1891990-08-0101 August 1990 Dcrdr Human Engineering Discrepancy Repts 1988 Summary Addendum 1,Vol 1 ML20006E3671990-01-11011 January 1990 Toledo Edison Co Mark-BZ Fuel Assembly Seismic & LOCA Analysis. ML20094J0841989-12-0808 December 1989 Investigation of Acoustic Leak Monitoring for NRC Region Iii. Info Partially Deleted ML19324C1761989-10-30030 October 1989 Hpi/Makeup Nozzle Weld Overlay Repair Contingency Plan. ML19327B0161989-10-11011 October 1989 Cycle 7 LOCA Limits. ML20245K6751989-08-0202 August 1989 Rev 2 to Review 18 Month PM Items for Diesel Generator & Evaluate Extension to 30 Months ML20151Z1941988-08-11011 August 1988 Rept on Reactor Vessel Continuous Vent Line Performance, ML20234F2501988-01-0606 January 1988 Rev 3 to App R Compliance Assessmemt Rept ML20147C0851987-12-0101 December 1987 Fifth Refueling Outage Executive Summary. Related Documents Encl ML20237J9781987-08-24024 August 1987 Performance Indicators for Davis-Besse Nuclear Power Station,Salp 6,Weekly Rept 3 for Period Ending 870824 ML20214J1891987-05-0505 May 1987 Rev 2 to App R Compliance Assessment Rept ML20206J5001987-03-31031 March 1987 Dcrdr Special Study Plans for Davis-Besse ML20212G7461987-01-0707 January 1987 Rept of Emergency Evacuation Review Team on Emergency Response Plans for Perry & Davis-Besse Nuclear Power Plants ML20214E0761986-11-17017 November 1986 Auxiliary Feedwater Calculation Summary ML20211E0651986-09-26026 September 1986 Transient Assessment Program Rept,Davis-Besse Unit 1 Reactor Trip on High Flux,840302 ML20214T7501986-09-11011 September 1986 DB Small-Break LOCA Analysis Assumptions Evaluation ML20154Q6531986-02-28028 February 1986 Westinghouse Owners Group Position on Davis-Besse Event ML20141E6691985-11-30030 November 1985 B&W Owners Group Action Plan for Review of 850609 Davis-Besse Transient ML20138H4891985-11-25025 November 1985 Rev 17 to Seismic Category I Piping Sys Support & Hanger Discrepancies ML20136H0951985-11-15015 November 1985 Revised Davis-Besse Reactor Protection Sys Single Failure Analysis ML20137H3971985-11-12012 November 1985 Rev 16 to Seismic Category I Piping Sys Support & Hanger Discrepancies Summary Rept ML20137S9031985-10-29029 October 1985 Toledo Edison Davis-Besse Nuclear Power Station Unit 1 Seismic Category I Piping Sys Support & Hanger Discrepancies,Summary Rept ML20209H5861985-10-28028 October 1985 Rev 3 to Course of Action ML20137S8241985-10-22022 October 1985 Rev 14 to Seismic Category I Piping Sys & Hanger Discrepancies,Summary Rept ML20209H6481985-10-15015 October 1985 Rev 3 to Auxiliary Feedwater Pump Turbine Overspeed Trip Throttle Valve Problem ML20138J4811985-10-15015 October 1985 Seismic Category I Piping Sys Support & Hanger Discrepancies ML20133M9911985-10-0808 October 1985 Rev 12 to Seismic Category I Piping Sys Support & Hanger Discrepancies,Summary Rept ML20133K9881985-10-0404 October 1985 Independent Mgt Assessment of Toledo Edison Davis-Besse QA Program ML20138A9411985-09-24024 September 1985 Rev 10 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20132E4471985-09-17017 September 1985 Rev 9 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20137C3021985-09-0909 September 1985 Toledo Edison Co Davis-Besse Nuclear Power Station Course of Action Rept ML20137M5431985-09-0909 September 1985 Vols 1 & 2 of Davis-Besse Course of Action ML20135D7421985-09-0303 September 1985 Rev 7 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20133K9941985-08-30030 August 1985 Rept of Assessment of Actions at Davis-Besse Resulting from 850609 Loss of Feedwater Event ML20134Q0161985-08-27027 August 1985 Rev 6 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20137U3061985-08-16016 August 1985 Rev 5 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20134B8371985-08-0909 August 1985 Rev 4 to Safety-Related Piping Sys Support & Hangar Discrepancies, Summary Rept ML20133M3261985-07-26026 July 1985 Rev 3 to Safety-Related Piping Sys Support & Hanger Discrepancies,Summary Rept ML20126L9021985-07-0505 July 1985 Rev 1 to Action Plans 5,6 & 7, Steam & Feedwater Rupture Control Sys Trip/Msiv Closure 1999-05-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20217D5441999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20210Q8541999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20209E6231999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20195F4871999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20207F4351999-05-0404 May 1999 Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504 ML20206M6341999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Davis-Besse Nuclear Station,Unit 1.With ML20205M2931999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Davis-Besse Nuclear Power Station.With ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20195D0001998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With ML20237E3171998-08-21021 August 1998 ISI Summary Rept of Eleventh Refueling Outage Activities for Davis-Besse Nuclear Power Station ML20237B1681998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236U5011998-07-23023 July 1998 Special Rept:On 980624,Unit 1 Site Damaged by Tornado & High Winds.Alert Declared by DBNPS Staff,Dbnps Emergency Response Facilities Activiated & Special Insp Team Deployed to Site by Nrc,As Result of Event ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A4121998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20196B5221998-05-23023 May 1998 10CFR50.59 Summary Rept of Facility Changes,Tests & Experiments Dbnps,Unit 1 for 960602-980523 ML20236E7581998-05-19019 May 1998 Rev 0 to Davis-Besse Unit 1 Cycle 12 Colr ML20236N7501998-04-30030 April 1998 Rev 2 to Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit ML20247F6721998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Davis-Bess Nuclear Power Station,Unit 1 ML20249A4141998-04-30030 April 1998 Revised Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20217P8041998-04-0707 April 1998 11RFO OTSG ECT Insp Scope ML20216B4041998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20216C5131998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20202D3721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20199G6321998-01-26026 January 1998 Rev 1 to Davis-Besse Unit 1,Cycle 11,COLR ML20198R4771998-01-13013 January 1998 SER Approving Second 10-year Interval Inservice Inspection Program Plan Requests for Relief for Davis-Besse Nuclear Power Station,Unit 1 ML20198K7931997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20217K6401997-12-31031 December 1997 1997 Annual Rept First Energy ML20203A3931997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Davis-Besse Nuclear Power Plant,Unit 1 ML20198S5371997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Davis-Besse Nuclear Power Station ML20217H7701997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20216H3261997-08-31031 August 1997 Monthly Operating Rept for August 1997 for DBNPS ML20217K0241997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Davis Besse Nuclear Power Station,Unit 1 1999-09-30
[Table view] |
Text
. . - -. -- . - _~.
hf 9 N$
g
' TITLE: Action Plan Report for NI-1 Source Range Channel REPORT BY: M. L. Borysiak PLAN NO.: 15A-1 15A-2 DATE PREPARED June 17, 1985 INTRODUCTION l l
The impact of NI-1 being declared inoperable prior to and during the l
. transient and the subsequent problem of NI-2 failing to respond when the high voltage was turned on to the detector was to enter the action state-ment of Technical Specification (T.S.) 3.3.1.1 after the reactor tripped.
Action Statement 6 of T.S. 3.3.1.1 simply stated is, if both source range ,
channels are inoperable, verify compliance with the Shutdown Margin requirements of T.S. 3.1.1.1 within one hour and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. The Shutdown Margin requirements were verified and documented in the Reactor Operator's log. Thus, there was no significant impact during or following the transient due to the NI-1 being declared ;
inoperable other than creating an undesirable added distraction to the operators in having to verify the Shutdown Margin requirements. NI-1 was subsequently declared operable at approximately 0400-0500 on June 9, 1985, i upon the successful completion of ST 5091.01, Source Range Functional Test.
l The problems with NI-1, as specified in the " Summary of Data" section of l this report have existed since prior to initial start-up. Past efforts to eliminate these problems have succeeded in reducing these problems, but not the total elimination thereof. The problems with NI-1 appear to be an annoyance and distraction to plant operations rather than a significant impact on plant operations.
Even though there appears to be no significant impact on plant operations, it is still highly desirable to correct these problems.
SUMMARY
OF DATA
- 1. Collect and analyze known information/ operational data for conditions prior to, during, and after the transient.
Past history and documentation with' respect to the NI-1 problem has ,
been 'obtained from Information & Records Management System,- Davis-Besse Maintenance Management System and the M-535 specification file. Due to this review and from discussions with L. C. Stalter, K. A. Yarger, T. R. Isley, and J. M. DeSando and from personal' involvement since 1978, these problems have existed since prior to the initial start-up.
The operational data for conditions prior to, during and after the l transient are as follows. On June 4, 1985, NI-1 was declared inoper- i able due to it reading E 1.5 decades above NI-2 with the High. Voltage Cut Off (NVCO) in effect. NI-1 was inoperable during the trip. At approximately 0400-0500 on June 9, 1985, ST 5091.01 was completed and the NI declared operable.
8507300154 850617 PDR P
ADOCK 05000346 4
PDR 1 of 2 I
__. _ _ ~___. _ .._ _ r m_..____,__.__
There are two, what would appear to be, mutually exclusive problems associated with the NI-1 Source Range Nuclear Instrumentation ch.snnel. l The first problem deals with the intermittent erroneous count rate indication when both the HVC0 is in effect and when it is not. The second deals with an intermittent spiking problem which occurs when the HVCO'is in effect and when it is not.
- 2. Review maintenance and test history.
A review of the maintenance history indicates that five work orders have been written since January of this year on the problems of spiking and erroneous counts. No significant results were obtained in determining the root cause of either problem. The required surveillance test, tests the equipment within the RPS cabinets.
Historically, these tests have not shown any problems.
CHANGE ANALYSIS Since 1977, the boron trifluoride detectors, pre-amp sud cable in Contain-ment have been replaced, along with modules in the RPS and a reworking of the grounds on the pre-amp and Count Rate Amplifier Module (CRAM) connec-tions with no positive effect on the total elimination of the spiking problem nor the erroneous / elevated count rate.
HYPOTHESES I. Possible intermittent problem within the CRAM causing erroneous counts.
II. Erroneous counts being induced from outside the RPS cabinet, i.e., in cable from penetration to CRAM.
III. Intermittent spiking problem induced from other equipment / cables in proximity to the manufacturer's supplied non-shielded cable.
IV. Intermittent spiking problem caused from ground loops between systems.
, V. Signal cable length for NI-1 is such that the length is terminated in a k, \, or full wave length to be susceptible to a low frequency of 45-60 Hz., i.e, the cables resonant frequency.
NOTE: Past efforts to identify the root cause suggest that the planned actions may not be totally successful in identifying the root causes. If these problems cannot be eliminated, the only
~
alternative would be to use the future Source Range indications that will be installed as part of the new Neutron Flux Monitoring
. Systems as per Regulatory Guide 1.97. This particular Facility Change Request (FCR 84-116) has been budgeted and is presently in the detailed design stage.
dd b/13 2 of 2 r __ _ _
.: .sr.:
~
r a r , ,,, ,u . .. rAies 4CilON PLAN
't** Rev. 0 15A-1 1 "' 2 -- .
rasi em rasu o ens e-44a o ov v.a u NI-l Source Range Nuclear Instrumentation Channel 6/18/85 H. L. Borysiak
,ri as ic n,oe c:in Pltn for testing hypotheses for the intermittent elevated count rate.
(Hypotheses I, II & V) ,, _
l'fil8.ti. A50 er.rdt is START TAHGET DATE STEP
@ppogg ACI b d l148 Sh iti$tilli 4 T V, TO DATE DATE COMPS ETED t
"All steps of this Action Plan are to be performed in accordance , , _
with the latest revision of " Guidelines to Follow When Trouble- __
chooting or Performing Investigative Actions into the Root.
Causes Surrounding the June 9, 1985 Reactor Trip". -- .- - -
I,
[
These Action Plan steps may.be performed in any order. }
1.- Determine /further isolate'the problem. . . ._
A. Take readings on the Count Rate Amplifier Module,(CRAM) test M. Borysiak. T. Isley --
jacks J3, J4 and JS on both NI-l and NI-2 with and without J. DeSando . .
s the High Voltage (HV) on, when unit is shutdown (Mode 5). - -
g ._
I B. Repeat step A only with HV off when unit is at power (Mode 1)' M. Borysiak. T. Isley i J. DeSando * --
When elevated count rate appears, repeat step A or B. M. Borysiak T. Isley .
l C. , .
J. DeSando
! I M. Borysiak i D. Evaluate results obtained and determine / plan next step in M. Boryslak' T. Isley I J. DeSando
~
ident Ifying rnot canine. Babcock & .
Wilcow k
. . . . _. .___ .., _ _ _ _ . - _ _ . _ __ _ ._.._.._.__._m _ . . . _ . . . _ _ _ _ _ _ _ _ _ _ .._ . . . _ . . . . ..
" ^ " ' ' ' 8 ^' "
ACTIOrJ PLAN
, m. , Rev. 0 15A-1 2
. -- ,, , ,,, pg, y,g, g ,,,,,.,,,g, i N1-1 Source Range Nuclear Instrumentation Channel 6/18/85 H. L. Borysiak
.n i o et neue cuive Plcn for testing hypotheses for the intermittent elevated count rate. (Hypotheses 1. II & V) . . . - . . . .
ruius Am.nl o srAnt ranus i n4 t sit" nuentnl, Action sites lnrsronsitin ery to nAtc out conet.t i s n
- 2. Cable Check. f ,
I A. Using a calibrated Time Domain Reflectometer, accurately M. Borysiak T. Isley
, measure the signal cable length of NI-1 and NI-2 (NI-2 for - .. ._
J. De Sando .-.. ____. . .
reference). Also check signal lead, outer shield and inner I shield for anomalies. _.
B. Calculate resonant frequency of cable. M. Borysiak T. Isley _ . _ . .
J. DeSando .
C. Walkdown conduit / cable looking'for possible sources that M. Borysiak T. Isley _
may induce noise in close proximity to the conduit / cable.
_J. DeSando (Specifically 60 HZ, AC equipment). . ... . -
+' - - '* - ~ " - - - -"
& * * " ' " * ~
. e y O.w-hW.h N- D'N =. .
- = ' ' ' * .. *8' *h * . "' &W"'*M* 8'" "'***%DM'"' S
, p ,, mog,,.-eeq .+e-e4 g
,- . . -== a - e - . -=+.e- . = = = = . - -
g . , . . s . . -
_ . _ . . . . . _ _ _ . _ - . _ _ _ _ _ _ .m .. __ _ _ _ . . . _ _ ___..__-._m _ . _ _ _ . . _ _ _ _ _ . . , _ _ _ , _ . . _ _ , , _ m - - _ - ~ __.
i ACTION PL AN .
8 M4 **"wd n r ea .6 i
Rev.0 15A-2 ~
1 >'
2' '.;
siv e's oa ri r ntrane n . n u ;p e e , o r NI-1 Source Range Nuclear Instrumentation Channel 6/18/85 M. L. Borystak'
.re co nc e.n s creve _ ._ , _ _ _ _ _ _
~ . .$b_."
- **IIk".8_hypothesesfortheintermittentspikingproblem.
(Hypotheses III & IV) ., _
i
- l sige eiu m mo ast o s r aHi
raupatn' H8 mulpet ti v -
TO DATE DA si O d.1PL t il D ,
1 i
- "All steps of this Action Plan are.to be performed in accordance ,
4-with the latest revision of " Guidelines to Follow when Trouble-shooting or Performing Investigative Actions into the Root l
Causes Surrounding the June 9, 1985 Reactor Trip". - __ .- _ . . .. . . .
b These Action Plan steps may be performed in any order. -
2 i
- 1. .
Have operators monitor and log any spiking problems observed. M. Borysiak T. Isicy
- t. '
p - !
. . . - ~ .
- 2. From drawings, ver y shielded vergs non- fiep ed manu{acturer M. Boryslak M. Borysiak 6/13/85l si. . . _ ._ . . . _ _ _ , , _ , ,
supplied cable from equipment in Control Room to Reactor Pro-d< _. ,
tection System (RPS). - - ---
J.
- 3. List of equipment in Control Room connected to RPS cabinet via M. Borysiak. ~T. Isley .-
-i i mar.ufacturer supplied cable and the routing of that cable J. DeSando ;
I I
! (conduits / cable trays / wireways).
._ _.. _ _ _ . . . . __ _ _ ~ _ . . - _ _ . - - - . . . . - - - -. - . - . . . . - _ . _
i !
j A. From the above. routings,' determine what other cables also M. Boryslak, T. Isley
.I $. _ _
e ,
' ACI(O*J l'l AN e e at4 raisuus n - i. 4 4,t *
.e ..e a . Rev. 0 15A-2
,DA 4 4 FHf PA6H H
. 2 d i.4 L 6 i Hi Peht la en NI-1 Source Range Nuclear Instrumentation Channel 6/18/85 M. Borysiak
.Pi o,ic .m. cievi Plan for testing hypotheses for the intermittent spiking problem. (Hypotheses III and IV) site l' Action stri=; """' l ^""*""8 Si^"I, ti 8 "' "-
tan nt u; ne worronni n y in OArc I nai
^"' 's v a mt l ia u 6
run in that routing.' , J. DeSando ,
I
- 4. , List of cables exiting RPS cabinet, destination and. routing. _
M. Borysiak T. Isley _
+ -.. -- . _ . _ . -
J. DeSando i l i A. -From the above routings, determine what other cables also M. Boryslak T. Isley I
J. DeSando I
i
- 5. Analyze the information obtained in steps 1 through 4, correlate M. Borysiak. T. Isley i
{withpast.spikingproblemsanddevelop.furthertests., ,
J. DeSando i
e l-l j .-- !
l i !
t
. I .
I i
i 1