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Category:EXAMINATION REPORT
MONTHYEARML20126L4921992-12-24024 December 1992 Exam Rept 50-155/OL-92-02 on 921201-03.Weaknesses Noted W/ Regard to Security & Implementation of EOPs During Simulator Exam.Exam Results:Both Crews Passed NRC Requalification Exam ML20195B5781988-10-26026 October 1988 Exam Rept 50-155/OL-88-01 on 880830 & 1012.Exam Results:One Senior Reactor Operator Passed All Portions of Exams & One Senior Reactor Operator Candidate & Reactor Operator Failed Written Exam & Not Given Operating Exam ML20214B6381987-05-13013 May 1987 Exam Rept 50-155/OL-87-01 on 870414-16.Exam Results:One Reactor Operator & Two Senior Reactor Operators Passed Written & Oral Exams.Exam & Answers Keys Encl ML20199F0141986-06-19019 June 1986 Exam Rept 50-155/OL-86-01 on 860506-08.Exam Results:All Four Senior Reactor Operator Candidates Passed Written & Operating Exams 1992-12-24
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000155/19990051999-09-30030 September 1999 Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted.Major Areas Inspected: Routine Decommissioning Insp Covered Aspects of Facility Mgt & Control & Decommissioning Support Activities IR 05000155/19990041999-08-12012 August 1999 Insp Rept 50-155/99-04 on 990609-0730.No Violations Noted. Major Areas Inspected:Aspects of Facility Mgt & Control, Decommissioning Support Activities Including Security, Spent Fuel Safety & Radiological Safety IR 05000155/19990031999-06-21021 June 1999 Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted. Major Areas Inspected:Facility Mgt & Control,Decommissioning Support Activities,Spent Fuel Safety & Radiological Safety IR 05000155/19990021999-04-26026 April 1999 Insp Rept 50-155/99-02 on 990226-0415.No Violations Noted. Major Areas Inspected:Aspects of Facility Mgt & Control, Decommissioning Support Activities,Spent Fuel Safety & Radiological Safety IR 05000155/19990011999-03-19019 March 1999 Insp Rept 50-155/99-01 on 990113-0225.One non-cited Violation Noted.Major Areas Inspected:Aspects of Facility Mgt & Control,Decommissioning Support Activities,Spent Fuel Safety & Radiological Safety IR 05000155/19980091999-01-15015 January 1999 Insp Rept 50-155/98-09 on 981201-990112.No Violations Noted. Major Areas Inspected:Licensee Management & Control, Decommissioning Support Activities,Sf Safety & Radiological Safety IR 05000155/19980081998-12-0303 December 1998 Insp Rept 50-155/98-08 on 980827-1130.No Violations Noted. Major Areas Inspected:Radiological Safety IR 05000155/19980071998-10-14014 October 1998 Insp Rept 50-155/98-07 on 980827-1007.No Violations Noted. Major Areas Inspected:Facility Mgt & Control,Physical Security,Spent Fuel Safety & Radiological Safety IR 05000155/19980061998-09-0303 September 1998 Insp Rept 50-155/98-06 on 980716-0826.No Violations Noted. Major Areas Inspected:Aspects of Licensee Mgt & Control, Decommissioning Support Activities,Spent Fuel Safety & Radiological Safety ML20195C6211998-08-18018 August 1998 EN-98-059,informing Commission That Staff Intends to Exercise Broad Discretion Pursuant to Section VII.B.6 of Enforcement Policy & Not Issue NOV or Propose Civil Penalty for Severity Level II Violation Identified by Licensee IR 05000155/19980051998-07-24024 July 1998 Insp Rept 50-155/98-05 on 980528-0715.No Violations Noted. Major Areas Inspected:Licensee Mgt & Control,Decommissioning Support Activities,Spent Fuel Safety & Radiological Safety IR 05000155/19980031998-06-16016 June 1998 Insp Rept 50-155/98-03 on 980407-0527.Violation Noted.Major Areas Inspected:Licensee Mgt & Control,Decommissioning Support Activities,Spent Fuel Safety & Radiological Safety IR 05000155/19980021998-04-21021 April 1998 Insp Rept 50-155/98-02 on 980203-0406.No Violations Noted. Major Areas Inspected:Licensee Mgt & Control,Decommissioning Support Activities,Spent Fuel Safety & Radiological Safety ML20202J8471998-02-14014 February 1998 Notice of Violation from Insp on 971205-980202.Violation Noted:Chemical Decontamination Worker Working Under RWP B982035 in High Radiation Area for Approx 55 Minutes & Did Not Monitor Dosimetry Time ML20203A0141998-02-14014 February 1998 Insp Rept 50-155/97-15 on 971205-980202.Violations Noted. Major Areas Inspected:Facility Management & Control, Decommissioning Support Activities,Spent Fuel Safety & Radiological Safety ML20199A2571997-12-30030 December 1997 EN-97-117:on 980105,informs Commission That Order Prohibiting Involvement in NRC-licensed Activities Issued to Dt Rich.Action Based on Investigation Conducted by Oi,Which Determined on 960721 & 0915,DT Rich Falsified Records IR 07100008/20120041997-12-17017 December 1997 Notice of Violation from Insp on 971008-1204.Violation Noted:On 971029,items Hanging from Spent Fuel Pool Rail Span 19 Had Combined Weight of 497 Pounds.Length of Time That Weight on Rail Exceeded Weight Restriction Not Determined ML20197E5901997-12-17017 December 1997 Insp Rept 50-155/97-13 on 971008-1204.Violations Noted. Major Areas Inspected:Major Aspects of Licensee Decommissioning Activities,Including Facility Mgt & Control, Decommissioning Support & Spent Fuel Safety Controls IR 05000155/19970101997-11-26026 November 1997 Insp Rept 50-155/97-10 on 970802-1007.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20199J4571997-11-19019 November 1997 Notice of Violation from Insp on 961216-971107.Violations Noted:Certain Radiation Surveys Required by Station Procedure RP-29,not Completed.Also Certain Radiation Survey Records Required to Be Maintained,Not Accurate IR 05000155/19970121997-10-17017 October 1997 Insp Rept 50-155/97-12 on 970812-1007.Violations Noted.Major Areas Inspected:Miscellaneous Security & Safeguards Issues IR 05000155/19970091997-10-0909 October 1997 Insp Rept 50-155/97-09 on 970617-0804.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering ML20211J7341997-10-0606 October 1997 Notice of Violation from Insp on 970902-05.Violation Noted: on 970902,maintenance Worker Preparing to Participate in Reactor Head Detensioning Operations Laid Down in Contaminated Area for Several Minutes IR 05000155/19970111997-10-0606 October 1997 Insp Rept 50-155/97-11 on 970902-05.Violations Noted. Major Areas Inspected:Various Aspects of Licensee Chemistry Radiation Protection Programs ML20217J3391997-08-12012 August 1997 Notice of Violation from Insp on 970303-0428.Violation Noted:On 970202 Rj Flowers,Employee of Consumers Power Co, Did Not Exit High Radiation Area After Receiving Alarm on Electronic Dosimeter as Required ML20217K5521997-08-12012 August 1997 Notice of Violation from Insp on 970303-0428.Violations Noted:Licensee Failed to Properly Evaluate Potential Radiological Hazards Associated W/Transfer of Highly Contaminated Filters ML20151J7721997-07-22022 July 1997 Notice of Violation from Insp on 970430-0616.Violation Noted:Inspector Identified That on 960403 & 970502,seven & Five CRDs Respectively Were Left After Insertion Time Testing W/Insert Speeds Greater than 28 IR 05000155/19970081997-07-22022 July 1997 Insp Rept 50-155/97-08 on 970430-0616.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support PNO-III-97-055, on 970611,decision to Permanently Shut Down Plant Three Yrs Before Expiration of Operating License in Yr 2000.Capacity of 67 Megawatts & Future Needed Improvements Would Be Too Expensive.State of Mi Will Be Informed1997-06-11011 June 1997 PNO-III-97-055:on 970611,decision to Permanently Shut Down Plant Three Yrs Before Expiration of Operating License in Yr 2000.Capacity of 67 Megawatts & Future Needed Improvements Would Be Too Expensive.State of Mi Will Be Informed ML20140G8931997-06-10010 June 1997 Insp Rept 50-155/97-04 on 970313-0429.Violations Noted. Major Areas Inspected:Operations,Maint & Engineering ML20140G8851997-06-10010 June 1997 Notice of Violation from Insp on 970313-0429.Violation Noted:Procedures Were Not Followed,In That Required Working Clearances & Protective Tagging Were Not Obtained by Workers Prior to Performing Work Activities IR 05000155/19970071997-06-0606 June 1997 Insp Rept 50-155/97-07 on 970426-0501.No Violations Noted. Major Areas Inspected:Licensee Fire Protection Program IR 05000155/19970061997-05-23023 May 1997 Insp Rept 50-155/97-06 on 970428-0502.No Violations Noted. Major Areas Inspected:Review of Vehicles Barrier Sys,Audits & Self Assessment,Testing,Maint,Security Contingency Capability & Protected Area Detection ML20141J9951997-05-19019 May 1997 Insp Rept 50-155/97-05 on 970303-0428.Violations Noted. Major Areas Inspected:Event in Which Workers Entered Power Block While Reactor at 9% Power Level Prior to Performance of Adequate Evaluation of Area Radiological Conditions IR 05000155/19970031997-05-13013 May 1997 Insp Rept 50-155/97-03 on 970331-0404.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program PNO-III-97-012, on 970224,licensee Notified NRC Resident Inspector Ofc That Loose Radioactive Surface Contamination Spread Throughout Turbine Bldg,During Transfer of Radwaste Processing Filters from Temporary Storage Barrel1997-02-26026 February 1997 PNO-III-97-012:on 970224,licensee Notified NRC Resident Inspector Ofc That Loose Radioactive Surface Contamination Spread Throughout Turbine Bldg,During Transfer of Radwaste Processing Filters from Temporary Storage Barrel IR 05000155/19960121997-02-24024 February 1997 Insp Rept 50-155/96-12 on 961130-970117.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20135D4431997-02-24024 February 1997 Notice of Violation from Insp on 961130-970117.Violation Noted:Use of Inappropriate Surveillance Procedure Causing Uncontrolled Leak & Inline Relief Valve Lifting Due to Failure to Remove Installed Blank Flange IR 05000155/19960011997-01-29029 January 1997 Insp Rept 50-155/96-01 on 961019-1129.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20134C9421997-01-29029 January 1997 Notice of Violation from Insp on 961019-1129.Violations noted:961108 Operators Closed EC Number 1 Loop Inlet Valve (MO-7062) Making Number 1 EC Loop Inoperable & Operability Test Number 2 EC Loop Outlet Valve Not Performed within 1 H ML20133C5231997-01-0202 January 1997 Insp Rept 50-155/96-11 on 961202-06.Violations Noted.Major Areas Inspected:Radiological Protection & Chemistry Controls,Status of Rp&C Facilities & Equipment ML20133C5111997-01-0202 January 1997 Notice of Violation from Insp on 961202-06.Violation Noted: High Radiation & Contaminated Areas Was Not Posted W/Signs Bearing Radiation Symbol IR 05000155/19960071996-12-0606 December 1996 Insp Rept 50-155/96-07 on 960909-12.No Violations Noted. Major Areas Inspected:Emergency Plan & Procedures IR 05000155/19960061996-10-28028 October 1996 Insp Rept 50-155/96-06 on 960727-0906.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support PNO-III-96-064, on 961023,shutdown for Evaluation of Environ Qualification Data Made.Licensee Performed Preliminary Assessment of Effect of Higher than Anticipated Temp Profile on safety-related Electrical Equipment Located1996-10-24024 October 1996 PNO-III-96-064:on 961023,shutdown for Evaluation of Environ Qualification Data Made.Licensee Performed Preliminary Assessment of Effect of Higher than Anticipated Temp Profile on safety-related Electrical Equipment Located IR 05000155/19960051996-09-20020 September 1996 Insp Rept 50-155/96-05 on 960608-0726.No Violations Noted. Continued Attention Needed on Maint Work on Plant TS Required Equipment.Major Areas Inspected:Engineering,Maint, & Plant Support PNO-III-94-039, on 940517,two Persons,Russian Visitor & Interpreter Were Killed in Traffic Accident Near Charlevoix,Mi.Cause of Accident Under Investigation1994-05-18018 May 1994 PNO-III-94-039:on 940517,two Persons,Russian Visitor & Interpreter Were Killed in Traffic Accident Near Charlevoix,Mi.Cause of Accident Under Investigation IR 05000155/19930191993-12-21021 December 1993 Insp Rept 50-155/93-19 on 931020-1214.Violations Noted.Major Areas Inspected:Operational Safety Verification,Engineered Safety Feature Sys Walkdowns & Maint & Surveillance Activities ML20059C1031993-12-21021 December 1993 Notice of Violation from Insp on 931020-1214.Violation Noted:Results of Static Votes Testing at Final Asleft Torque Switch Setting for MO-7053 Were Not Evaluated Prior to Return to Svc of Valve IR 05000155/19930201993-11-10010 November 1993 Insp Rept 50-155/93-20 on 931025-29.No Violations Noted. Major Areas Inspected:Followup Insp of Previously Identified Edsfi Findings 1999-09-30
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U.S. NUCLEAR REGULATORY COMMISSION REGION III l
Report No. 50-155/0L-86-01 I Docket No. 50-155 License No. DPR-6 Licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 j j Facility Name: Big Rock Point Nuclear Power Station f
! Examination Administered At: Big Rock Point .
,' Examination Conducted: May 6, 7, and 8, 1986 I
Examiner:
T. .
1 organ
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6//9/8/,.
! Date b
Approved By: ' Operating
.'/k Licensing Section 02 M. Burdick, Chief fg Date Examination Summary Examination administered on May 6, 7, and 8, 1986 (Repor'. No. 50-155/0L-86-01))
Examinations were administered to four senior reactor operator candidates.
Results: All four senior reactor operator candidates passed the written and operating examinations.
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B606240169 860619 l PDR ADOCK 05000155 y PDR l
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, REPORT DETAILS
- 1.
- Examiners j *T. L. Morgan, INEL i
- 2. Examination Review Meeting I
At the conclusion of the written examination, the questions and answers were given to the facility training staff for review and comment. At the i exit meeting the facility supplied the examiner with their comments to the SR0 written examination. On the following pages are the facility comments and the examiner's resolution to each.
- 3. Exit Meeting i
At the conclusion of the site visit the examiner met with representatives of the plant site to discuss the results of the examinations. Those individuals who clearly passed the oral examinations were identified in this meeting. The examiner noted no discrepancies. I l
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J FACILITY EXAMINATION COMMENTS AND EXAMINER RESOLUTION FOR BIG ROCK POINT EXAMINATION ON MAY 6, 1986
] 1. Question 5.05B Facility Coment:
The candidates will not be able to answer the question about shallow rods, because Big Rock does not have them. However they should be able to discuss the high flux peaks, causing a unit derate, to prevent exceeding thermal limits.
Resolution:
1
- Coment is accepted, answer key will be modified to delete the shallow rod discussion and include the discussion on thermal limits and the derating. Point value remains the same.
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! 2. Question 5.10A j Facility Comment:
MAPLHGR: The candidates answer will vary slightly from the answer key.
The candidates will state that the MAPLHGR limit decreases initially due 4 to densification. They will state that the pellet first shrinks axially, and radially increasing the gas gap. (See Attached Reference A) then the i students answer will follow the answer key.
Resolution:
Coment is accepted, answer key will be modified to include decrease due
. to densification and the remainder of the answer will remain and point l value is unchanged.
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- 3. Question 5.10B Facility Comment:
The candidates will answer that MAPLHGR limits prevent clad temperature from reaching 2200"F during a L.0.C.A. to prevent clad failure (See i
AttachedReferencesB)
Resolution:
i Comment is accepted, answer key will be modified to accept limiting fuel 1 temp to 2200 F during a LOCA. The point value remains unchanged.
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- 4. Question 6.03D Facility Comment:
The candidate may be very specific about the differences in the Yarway l Steam Drum level sensors. In that one utilizes an 50 inch or 25 inch using 0 as a midpoint reference column. While the other has an 80 inch or 40 inch with 0 as a midpoint reference column.
Resolution:
Comment noted, no change to the answer key required.
- 5. Question 6.04B Facility Comment:
Technical Specification state two reasons for the 120 sec. timer. Full consideration should be given both. (See Attached Reference C).
Resolution:
Comment is accepted, the answer key will be modified to add the second answer. Both answers will be required for full credit. Point value will remain the same, each answer will be worth 0.25 each.
- 6. Question 6.04D j Facility Comment:
This question asks what operation ACTION, but the answer key only gives full credit for three separate responses, any one of which meets the question criterion. Full credit should be given any correct singular
- response.
Resolution:
Ccmment is accepted, due to the miss wording of the question. The answer key will be changed to accept any one of the three possible answers for full credit. The point value will remain unchanged.
- 7. Question 6.05B l
Facility Comment:
Candidate may answer three of three switches all below the 125 X 10E-5% !
range (See Attached Schematic Reference D) !
Question 6.05C Facility Comment _:
I Candidate may answer three of three switches below the 125 X 10E-7% range 4
(See Attached Schematic Reference D) 4 i
Resolution:
Coments are noted. This is stating the same thing as the answer key.
No changes required.
- 8. Question 6.08 Facility Comment:
There does not appear to be adequate information given to answer this question. The examiner references question bank question No. 13, Technical Data Book 15.5.f.7 and ch. 29 Reactor Systems pg 29-5 and 29-6 (all have been attached and marked E). These reference all discuss an open from the thermocouple. The question is about a short. We took The question to the Plant Instrument and Control staff, and their answer to us was that they could not answer the question as to the reading produced by the thermocouple. It is our position that since this is a three part question, with each part depending on a correct response in part one, the question should be eliminated from this test.
Resolution:
Coment noted. The question will not be deleted, because it is already taken into account that the subparts of this question are dependent upon the answers to the previous portion. Part a's answer is being changed to 2 or 3. This is due to examiner error when developing the question and miss wording of choices. Part a remains as is because, any where that the short is assumed to be the temperature will be lower than at the thermocouple, if the candidate answers part a as 2 then part b is 2 and c is 2. The answer key will be added to reflect these changes. The point value remains the same.
- 9. Question 6.098 Facility Comment:
In September 1985 the Emergency Condenser Outlet Valves power supplies were moved to the Alternate Shutdown system 125 VDC battery. The change was due to Appendix R requirements. The new power now is Alternate Shutdown battery BKR 72-2011 and 72-2012 (8KR No. not necessary in answer).
Resolution:
This comment is for Question 6.09A not part B, as indicated initially.
The coment is accepted and the answer key will be modified to indicate batteries vis DC MCC. The point value will remain as is.
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- 10. Question 6.11 l Facility Coment:
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Students may respond in BRP comon lingo:
1 i 1. No Coment
- 2. Recirc Valve Closure
- 3. M.S.I.V. (Main Steam Isolation Valve Closure)
- 4. No Coment
- 5. Low Condenser Vacuum Resolution:
- Coment noted, this is stating the same thing as the answer key.
No modification is required.
- 11. Question 7.04
! Facility Comment:
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Candidates may answer if deliberately poisoning all poison must be injected with no termination.
j Resolution:
i l Coment noted. This is paraphrasing the answer key. Exact wording is not required for full credit. No change to the answer key or point value.
! 12. Question 7.06A Facility Coment:
, There are additional actions that the candidates might list, i
Resolution:
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- Comment accepted, the additional actions will be added to the answer key. The point value will remain the same but will be equally divided !
between all possible responses. ,
- 13. Question 7.08 l Facility Coment: .
I
) When the Scram dump tank is bypassed: Candidates may say when the mode
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switch is in bypass dump tank position (BDTP).
! Resolution: .
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Coment noted. Exact wording is not required to get full credit, i paraphrasing is acceptable. t i
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- 14. Question 7.09B 1
Facility Coment:
. The Recirc pump discharge butterfly valves have no position indication.
(They have been electrically disabled and locked in the open position.)
Resolution:
i i Coment accepted. Due to the valve being disabled and no indication 4
available part b will be deleted from question. The point value will be decreased by 0.5. Section and test totals will be adjusted accordingly.
! 15. Question 7.11 Facility Coment:
i The candidates may also include Item 1: of E.M.P. 3.3 as part of the j answer. (SeeAttachmentF) 1
- Resolution
I Coment not accepted. Referene* F only applies to the Loss of Coolant Procedure while the question ro ers to all the emergency procedures and l there guidelines. Answer key and point value remains unchanged.
! 16. Questiun 8.01 I
l Facility Comment: '
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Candidates may also answer temporary change no change of intent. (See Attachment G Admin. Procedure and Tech. Specs.)
, Resolution:
i Coment noted. The question specifically asks about revisions not i temporary changes. If the candidate answers for revision and temporary -
! change full credit will be given if only temporary change is discussed then partial credit will be given. Answer key and point value will remain unchanged.
! 17. Question 8.03
! l Facility Coment:
answer On Call Technical Advisor instead of S.T.A. or l The Shift candidate Engineer. may(Big Rock change to a 0.T.A. in 1982) l i
j Resolution: ;
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! Comment accepted. The title of 0.T.A. or On Call Technical Advisor will l be added as an alternate title. The point value will remain as is, i
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- 18. Question 8.10
- Facility Coment
The candidate may answer that a trip must be placed in on an affected
, channel. This action produces a scram should a trip occur on one of the
! remaining two (See Attachment H) 1 j Resolution:
f Comment accepted. The answer key will be modified to include this l statement. The question did not ask how the conditions were accomplished l J
but what was required condition.
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! 19. Question 8.13b l
Facility Comment: i
! The candidate will probably answer using the entire vacuum relief train. ;
i (See Attachment I) Also the integrity of Containment is more than just l
- protecting the structure. So the closing and reclosing after vacuum f relief may appear in the candidates answer. (SeeAttachmentJ) l
)
i Resolution:
i Coment partially accepted. The candidate answer using the entire vacuum '
i relief operation as described in Attachment I answers the question.
1 (Attachment I exceeds the requirements for full credit) The second i portion of the coment referring to what integrity is and when it is j required is not asked for in the question and, therefore, will not be j accepted. The answer key and point value will not be changed.
i i 20. Question 8.14 .
i Facility Coment:
l l Big Rock uses a 30 day interval 30 days X 1.25 = 37.5 days not 7.75. i j
i Resolution:
i Coment is accepted. Due to examiners error 31 days was used for the i monthly interval vis 30. The answer key will be modified to 7.5 vis 7.7!>
j and 1.5 vis 1.75 respectively. Point value will remain the same.
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i l EXAMINER COMMENTS '
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j Section Corrections Made During Grading
- 5.06 Will is misspelled in the second line of part B.
- 6.07 A should be 4 vis 3, typo.
6.09 C changed " circuit does not indicate open" top " circuit is not open."
Examiners misinterpretation of the reference materiel.
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! 8.08 Answer: The "or above" was not asked for in the question, there fore, it is assumed to be implied when the candidate states the E
- plan level or entry. Only the entry point is required for full
! credit.
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