ML18102A351: Difference between revisions
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Transition to a different shift rotation at this time would disrupt the current outage schedule and affect the manpower available to augment outage support. | Transition to a different shift rotation at this time would disrupt the current outage schedule and affect the manpower available to augment outage support. | ||
r-1 9609040267 960827 PDR ADOCK 05000272 I p PDR | r-1 9609040267 960827 PDR ADOCK 05000272 I p PDR | ||
Document Control Desk 2 LR-N96264 LCR S96-11 JUSTIFICATION OF THE REQUEST CHANGE 12-hour shifts provide for a reduced number of turnovers which allows for better communications and continuity. Shifts are trained as a team, and a change to 8-hour shifts would disrupt the team concept that has been established. | |||
The current 12-hour shift schedule has enjoyed a high-degree of acceptance among shift personnel, both workers and supervision alike. On the 12-hour shift schedule, personnel receive more consecutive time off, therefore, they are more rested when returning to work. There is less changing of shifts and therefore, personnel have sufficient time to adjust to the changes. | The current 12-hour shift schedule has enjoyed a high-degree of acceptance among shift personnel, both workers and supervision alike. On the 12-hour shift schedule, personnel receive more consecutive time off, therefore, they are more rested when returning to work. There is less changing of shifts and therefore, personnel have sufficient time to adjust to the changes. | ||
The change to the specifications will not allow routine use of overtime. In addition, TS 6.2.2.d identifies PSE&G's limits on overtime. The specification refers to Generic Letter 82-12 which defined appropriate limits on overtime for operating personnel. | The change to the specifications will not allow routine use of overtime. In addition, TS 6.2.2.d identifies PSE&G's limits on overtime. The specification refers to Generic Letter 82-12 which defined appropriate limits on overtime for operating personnel. | ||
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CONCLUSION Based on the above discussions and the no significant hazards consideration determination presented in Attachment 2, PSE&G has determined that the proposed changes do not adversely affect or endanger the health or safety of the general public or involve a significant safety hazard and are therefore acceptable. | CONCLUSION Based on the above discussions and the no significant hazards consideration determination presented in Attachment 2, PSE&G has determined that the proposed changes do not adversely affect or endanger the health or safety of the general public or involve a significant safety hazard and are therefore acceptable. | ||
Document Control Desk | Document Control Desk | ||
* LR-N96264 LCR S96-11 SALEM GENERATING STATION UNITS 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS 10CFR50.92 EVALUATION Public Service Electric & Gas company (PSE&G) has concluded that the proposed changes to the Salem Generating Station Unit 2 Facility Operating License and to the Salem Units 1 and 2 Technical Specifications(TS) do not involve a significant hazards consideration. In support of this determination, an evaluation of each of the three standards set forth in 10CFR50.92 is provided below: | * LR-N96264 LCR S96-11 SALEM GENERATING STATION UNITS 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS 10CFR50.92 EVALUATION Public Service Electric & Gas company (PSE&G) has concluded that the proposed changes to the Salem Generating Station Unit 2 Facility Operating License and to the Salem Units 1 and 2 Technical Specifications(TS) do not involve a significant hazards consideration. In support of this determination, an evaluation of each of the three standards set forth in 10CFR50.92 is provided below: | ||
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This change is administrative in nature and has no significant impact on the probabilities or consequences of any evaluated accident or malfunction of safety important equipment. | This change is administrative in nature and has no significant impact on the probabilities or consequences of any evaluated accident or malfunction of safety important equipment. | ||
Document Control Desk 2 | |||
* LR-N96264 Attachment 2 LCR 896-11 | * LR-N96264 Attachment 2 LCR 896-11 | ||
: 2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. | : 2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. | ||
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This is an administrative change and does not affect any margins of safety. Plant operation with the proposed revision to shift working hours has been found to improve operator morale and performance. | This is an administrative change and does not affect any margins of safety. Plant operation with the proposed revision to shift working hours has been found to improve operator morale and performance. | ||
CONCLUSION Based on the above discussion, PSE&G has determined that the proposed changes do not involve a significant hazards consideration. | CONCLUSION Based on the above discussion, PSE&G has determined that the proposed changes do not involve a significant hazards consideration. | ||
Document Control Desk LR-N96264 LCR 896-11 MARKED UP PAGES | |||
ADMINISTRATIVE CONTROLS | |||
ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF The facility organization shall be subject ~~ the fo:..lJwing: | |||
: a. Each on duty shift shall be composed of at least the minimum shift c::-ew composition shown in Table 6. 2-l;X". ~ | : a. Each on duty shift shall be composed of at least the minimum shift c::-ew composition shown in Table 6. 2-l;X". ~ | ||
: b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the Control Room area at all times. | : b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the Control Room area at all times. | ||
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()Orr>1no....j l ) \"I I t I $;" o pero... ti().1, SALEM - UNIT 1 6-2 Amendment No. 168 | ()Orr>1no....j l ) \"I I t I $;" o pero... ti().1, SALEM - UNIT 1 6-2 Amendment No. 168 | ||
(21 l Sum~ ~erfol""1ance (Section 6.3.3, Suoolement Sl (al Prior to resuming power opera ti on fo 11 o"'i ng tl'le first refueling outage, PSE!iG shall provide a detailed survey of insulation :naterials. | (21 l Sum~ ~erfol""1ance (Section 6.3.3, Suoolement Sl (al Prior to resuming power opera ti on fo 11 o"'i ng tl'le first refueling outage, PSE!iG shall provide a detailed survey of insulation :naterials. | ||
(bl Prior to operation above fi'le ;Jercent power, control ruom operators shall be trained in the recognition and mitigation of l?! performance de9radation. | (bl Prior to operation above fi'le ;Jercent power, control ruom operators shall be trained in the recognition and mitigation of l?! performance de9radation. | ||
(22) Radiation Protection Oraan.ization (Section 12.0, Suoolement Sl PSE&G shall c:Jnplete the reorganization actions and programs associated with radiation protection no later than November l, 1981. | (22) Radiation Protection Oraan.ization (Section 12.0, Suoolement Sl PSE&G shall c:Jnplete the reorganization actions and programs associated with radiation protection no later than November l, 1981. | ||
( 23 l | ( 23 l Category r 1'4asonry '..Ja 11 s (Section 3 .8 .3, Suoo l ement S) | ||
Category r 1'4asonry '..Ja 11 s (Section 3 .8 .3, Suoo l ement S) | |||
(al Prior to operation above f'fve oen:ent power, PSE!iG shall submit the information requested in the NRC letter dated January 8, 1981. | (al Prior to operation above f'fve oen:ent power, PSE!iG shall submit the information requested in the NRC letter dated January 8, 1981. | ||
( b) Pri o,. to startup fo 11 owing the first refuel i ng, PSBG sna 11 resolve the difference bet'#een the staff criteria and the criteria used by PSE&G to the satisfaction of tl'le NRC and implement tl'le required fixes tl'lat ~ight result fran such a re solution. | ( b) Pri o,. to startup fo 11 owing the first refuel i ng, PSBG sna 11 resolve the difference bet'#een the staff criteria and the criteria used by PSE&G to the satisfaction of tl'le NRC and implement tl'le required fixes tl'lat ~ight result fran such a re solution. | ||
(24) TI4I Action P1an Conditions (Section 22.2, Supplement 5) | (24) TI4I Action P1an Conditions (Section 22.2, Supplement 5) | ||
Unless other-.ise noted, each of the following conditions references the appropriate section of Supplement No. 5 to the Safety Evaluation Report (NUREG-0517) for the Salem Nuclear Generation Station, Unit 2, dated January 1981 and shall be completed to the satisfaction of the NRC by the times i ndi cate<1. | Unless other-.ise noted, each of the following conditions references the appropriate section of Supplement No. 5 to the Safety Evaluation Report (NUREG-0517) for the Salem Nuclear Generation Station, Unit 2, dated January 1981 and shall be completed to the satisfaction of the NRC by the times i ndi cate<1. | ||
PSE&G u arly scheduled eight-nour (b) Shor~-ienn lccicent ~nalysis and ~r~cedure ~evision | PSE&G u arly scheduled eight-nour (b) Shor~-ienn lccicent ~nalysis and ~r~cedure ~evision | ||
( ~ ei::: ~ on 22 . 2 , ! . C. l and : . ~ | ( ~ ei::: ~ on 22 . 2 , ! . C. l and : . ~ | ||
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*:mer'1ency ocerJtion instr*.Jct~on *..-itnin 30 effective f'lil | *:mer'1ency ocerJtion instr*.Jct~on *..-itnin 30 effective f'lil | ||
~ewer days of operation. | ~ewer days of operation. | ||
ADMINISTRATI'Ve: CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager - Salem Operations shall be responsible for overall facility operation and snall delegate in writing the succession to this responsibility during his absence. | |||
6.1.2 The Senior Nuclear Shift Supervisor or, during his absence from the | 6.1.2 The Senior Nuclear Shift Supervisor or, during his absence from the | ||
*Control Room, a designated individual shall be responsible for the Control Room command function. A management directive to this effect, signed by the Chief Nuclear Officer and President - Nuclear Business Unit, shall be reissued to all station.personnel on an annual basis. | *Control Room, a designated individual shall be responsible for the Control Room command function. A management directive to this effect, signed by the Chief Nuclear Officer and President - Nuclear Business Unit, shall be reissued to all station.personnel on an annual basis. | ||
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: a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1. T,._;.sE:Q..1 J SALEM - UNIT 2 6-1 Amendment No. 150 | : a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1. T,._;.sE:Q..1 J SALEM - UNIT 2 6-1 Amendment No. 150 | ||
.b; At least cne licensed :Reactor cpttator shall be in the cx:a1t:rol ro::::m | .b; At least cne licensed :Reactor cpttator shall be in the cx:a1t:rol ro::::m | ||
*when fuel is in the reactor. In ad:litiat, at least cne lioersed Senior Reactor q:ierator shall be in the a:rrt:.rol Rcan area at all tilll!!S. | *when fuel is in the reactor. In ad:litiat, at least cne lioersed Senior Reactor q:ierator shall be in the a:rrt:.rol Rcan area at all tilll!!S. |
Latest revision as of 04:28, 3 February 2020
ML18102A351 | |
Person / Time | |
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Site: | Salem |
Issue date: | 08/27/1996 |
From: | Public Service Enterprise Group |
To: | |
Shared Package | |
ML18102A350 | List: |
References | |
NUDOCS 9609040267 | |
Download: ML18102A351 (9) | |
Text
Document Control Desk LR-N96264 Attachment 1 LCR S96-11 SALEM GENERATING STATION FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS BASIS FOR REQUESTED CHANGE REQUESTED CHANGE AND PURPOSE The changes identified on Attachment 3 will remove the indicated License Condition from the Facility Operating License for Salem Unit 2. This is TMI Action Plan Item I.A.1.3 - Shift Manning.
Specifically, the condition states, "PSE&G shall establish regularly scheduled 8-hour shifts without reliance on routine use of overtime by June 3, 1981. 11 PSE&G is proposing to delete this license condition. PSE&G is also proposing to modify Technical Specifications (TS) Section 6.0 Administrative Controls to incorporate shift manning and limits on overtime. This will allow the continued use of a regularly scheduled 12-hour shift rotation without routine heavy use of overtime. In addition, TS 6.2.2.d identifies that PSE&G's limits on overtime are defined in Generic Letter 82-12.
BACKGROUND PSE&G has established a 12-hour shift schedule for the Hope Creek Nuclear Station. This schedule was approved by the NRC in Amendment 41 to the Hope Creek TS. PSE&G has also established a 12-hour shift rotation for Salem Nuclear Generating station.
However, it has been identified that the Salem Unit 2 Facility Operating License DPR-75 contains a license condition that stipulates 8-hour shifts. PSE&G is proposing to delete this license condition and incorporate the requirements with a change to 12-hour shifts into the Administrative Controls section of TS.
Salem Units 1 and 2 are currently shutdown and defueled. PSE&G will continue to operate on the established*12-hour schedule.
Transition to a different shift rotation at this time would disrupt the current outage schedule and affect the manpower available to augment outage support.
r-1 9609040267 960827 PDR ADOCK 05000272 I p PDR
Document Control Desk 2 LR-N96264 LCR S96-11 JUSTIFICATION OF THE REQUEST CHANGE 12-hour shifts provide for a reduced number of turnovers which allows for better communications and continuity. Shifts are trained as a team, and a change to 8-hour shifts would disrupt the team concept that has been established.
The current 12-hour shift schedule has enjoyed a high-degree of acceptance among shift personnel, both workers and supervision alike. On the 12-hour shift schedule, personnel receive more consecutive time off, therefore, they are more rested when returning to work. There is less changing of shifts and therefore, personnel have sufficient time to adjust to the changes.
The change to the specifications will not allow routine use of overtime. In addition, TS 6.2.2.d identifies PSE&G's limits on overtime. The specification refers to Generic Letter 82-12 which defined appropriate limits on overtime for operating personnel.
The limits specified in the generic letter are defined in PSE&G Nuclear Business Unit's Administrative Procedures.
CONCLUSION Based on the above discussions and the no significant hazards consideration determination presented in Attachment 2, PSE&G has determined that the proposed changes do not adversely affect or endanger the health or safety of the general public or involve a significant safety hazard and are therefore acceptable.
Document Control Desk
- LR-N96264 LCR S96-11 SALEM GENERATING STATION UNITS 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS 10CFR50.92 EVALUATION Public Service Electric & Gas company (PSE&G) has concluded that the proposed changes to the Salem Generating Station Unit 2 Facility Operating License and to the Salem Units 1 and 2 Technical Specifications(TS) do not involve a significant hazards consideration. In support of this determination, an evaluation of each of the three standards set forth in 10CFR50.92 is provided below:
REQUESTED CHANGE The proposed change to the Salem Unit 2 Facility Operating License deletes license condition 2.C(24) (a) Shift Manning. This condition, TMI Action Plan item I.A.1.3, required PSE&G to establish regularly scheduled 8-hour shifts without reliance on routine use of overtime by June 3, 1981. PSE&G initially complied with the condition as required, however, PSE&G has since established a 12-hour shift rotation that does not rely on regularly scheduled overtime. PSE&G is also proposing to modify Salem Units 1 and 2 TS, Section 6.0 Administrative Controls, to incorporate shift manning while changing from 8-hour to 12-hour shifts.
BASIS
- 1. The proposed change does not involve a significant increase in the probability or consequence of an accident previously evaluated.
The proposed change does not involve a physical or procedural change to any structure, system, or component that significantly affects the probability or consequences of any accident or malfunction of equipment important to safety previously evaluated in the Updated Final Safety Analysis Report (UFSAR). The proposed changes will permit the use of 12-hour shifts which average 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week and also satisfy the guideline in Generic Letter 82-12 for operating shifts.
This change is administrative in nature and has no significant impact on the probabilities or consequences of any evaluated accident or malfunction of safety important equipment.
Document Control Desk 2
- LR-N96264 Attachment 2 LCR 896-11
- 2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed revision involves no physical changes in the plant or to the manner in which plant systems are operated.
The change modifies the working hours per shift for operating personnel without significantly changing the hours worked per week and retains the current limitations on excessive overtime. The proposed changes are administrative in nature; therefore, no new or different accident is created.
- 3. The proposed change does not involve a significant reduction in a margin of safety.
This is an administrative change and does not affect any margins of safety. Plant operation with the proposed revision to shift working hours has been found to improve operator morale and performance.
CONCLUSION Based on the above discussion, PSE&G has determined that the proposed changes do not involve a significant hazards consideration.
Document Control Desk LR-N96264 LCR 896-11 MARKED UP PAGES
ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF The facility organization shall be subject ~~ the fo:..lJwing:
- a. Each on duty shift shall be composed of at least the minimum shift c::-ew composition shown in Table 6. 2-l;X". ~
- b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the Control Room area at all times.
- c. All CORE ALTERATIONS shall be observed and directly super*.rised by a licensed Senior Reactor Operator who has no other concurrent responsibili~~es during this operation.
- d. The amoi..:...~t ct overtime worked by plant staff members performing safety-related functions must be limited in accordance with the NRC Policy St:,:; ~.::rnent on working ~ours (Generic i:.er.r:.er No. 82-12)
- e. The Operating Engineer, Senior Nuclear Shift Supervisors, and Nuclear Shift Supervisors shall each hold a senior reactor cperatcr license. 7he Nuclear Cor.:rol Operators shall hold reactor ooerat::::r lice:i.ses.
- f. The Opera:ions Manager shal:.. rnee: or.e cf the following:
\1) Ho:..~ an SRO 2.i::::e::;se.
(2) Have held ar. SRO 2.i:::ense f::Jr a s1m12.ar ur.it :?WR).
Q..,j e be.
Ad e ~ ua..-+e .sh 1-4'-t C'c*v'e1 0 \..' c::: l t r{Y) e w 1Tho~T roLJt1ne.. he11.- y i.' u I o1e.r ~ -t lo S (:)er soi'" o e }
0 b jec.-l>>"e.. IS fa ha.\./ e.. I .
Lf O - hour wee
- k. w h1 1-e.. t- he.
vJ 0-1 k Cv
()Orr>1no....j l ) \"I I t I $;" o pero... ti().1, SALEM - UNIT 1 6-2 Amendment No. 168
(21 l Sum~ ~erfol""1ance (Section 6.3.3, Suoolement Sl (al Prior to resuming power opera ti on fo 11 o"'i ng tl'le first refueling outage, PSE!iG shall provide a detailed survey of insulation :naterials.
(bl Prior to operation above fi'le ;Jercent power, control ruom operators shall be trained in the recognition and mitigation of l?! performance de9radation.
(22) Radiation Protection Oraan.ization (Section 12.0, Suoolement Sl PSE&G shall c:Jnplete the reorganization actions and programs associated with radiation protection no later than November l, 1981.
( 23 l Category r 1'4asonry '..Ja 11 s (Section 3 .8 .3, Suoo l ement S)
(al Prior to operation above f'fve oen:ent power, PSE!iG shall submit the information requested in the NRC letter dated January 8, 1981.
( b) Pri o,. to startup fo 11 owing the first refuel i ng, PSBG sna 11 resolve the difference bet'#een the staff criteria and the criteria used by PSE&G to the satisfaction of tl'le NRC and implement tl'le required fixes tl'lat ~ight result fran such a re solution.
(24) TI4I Action P1an Conditions (Section 22.2, Supplement 5)
Unless other-.ise noted, each of the following conditions references the appropriate section of Supplement No. 5 to the Safety Evaluation Report (NUREG-0517) for the Salem Nuclear Generation Station, Unit 2, dated January 1981 and shall be completed to the satisfaction of the NRC by the times i ndi cate<1.
PSE&G u arly scheduled eight-nour (b) Shor~-ienn lccicent ~nalysis and ~r~cedure ~evision
( ~ ei::: ~ on 22 . 2 , ! . C. l and : . ~
- 3 )
7he ocerator! s~all be briefed on tne revisions ~o :ne
- mer'1ency ocerJtion instr*.Jct~on *..-itnin 30 effective f'lil
~ewer days of operation.
ADMINISTRATI'Ve: CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager - Salem Operations shall be responsible for overall facility operation and snall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Senior Nuclear Shift Supervisor or, during his absence from the
- Control Room, a designated individual shall be responsible for the Control Room command function. A management directive to this effect, signed by the Chief Nuclear Officer and President - Nuclear Business Unit, shall be reissued to all station.personnel on an annual basis.
I.
6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include positions for activities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. ~hese relationships shall be documented and updated, as appropriate, in the form ~f organization charts, functional descriptions of departmental r~sponsibilities and relationships, and job descriptions for key personnel positions, or in equivalen=
forms of documentation.* These requirements shall be documented ~~
the Salem Updated Final Safety Analysis Report and updated in accordance with 10 CFR 50.7l(e).
- b. The General Manager - Salem Operations shall be responsible for overall facility safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plants.
- c. The Chief Nuclear Officer and President - Nuclear Business Unit shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plants to ensure nuclear safety.
- d. The individuals who train the operating staff and those who carry out health physics and cruality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
f"'c..ve 6.2.2 FACILITY STAFF
-to 0e.ft"
~e.. The Facility organization shall be subject to the following:
~u... J
- a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1. T,._;.sE:Q..1 J SALEM - UNIT 2 6-1 Amendment No. 150
.b; At least cne licensed :Reactor cpttator shall be in the cx:a1t:rol ro::::m
- when fuel is in the reactor. In ad:litiat, at least cne lioersed Senior Reactor q:ierator shall be in the a:rrt:.rol Rcan area at all tilll!!S.
- c. All a:m: ~CNS shall be c:i::1Served an:i directly supmvise:i by a licensed Senior Reactor ~tor who has no other ccn::urrent respcnsibilities during this cperatiat.
- d. 'Ihe mmt of overtime W10rlced by plant staff ne** et'S perfomin; safety-related fun:::ticns DJSt be l.iJDit:ed in acx::crdance with the NRC Policy statement cri workin; hairs (Generic Letter No. 82-12).
- e. 'Ihe ~tin; Erqineer, Senior Nlci.ear Shit't SUpervi.scrs, ani Nlci.ear Shift .SUpervisors shall each hold a senior reactor cperator lioen;e. 'lbe Nllcl.ear a:ntrol cpttatcrs shall hold reactor c:p!rator lioerises.
- f. 'Ihe cp!raticns Manager shall meet cna of the followi.n;:
(1) Hold an SR:> license.
(2) Have held an SR:> liamse for a similar unit (~).
- T~sR..*
Ade i l.'U.. te.
vJ t-hc . .: T i
o b j e.c. t, ve....
Li.)01 k t LS ev ri o {'r')I n a.... I C) ref<l., t.i{) 5 I SAUM - UNIT 2 6-2 Amen::lme It No, il I