ML20127G917

Proposed Changes to Tech Specs Re Control Rod Block Instrumentation Setpoints,Administrative Controls,Offsite Organization,Unit Organization & Independent Safety Engineering Group.Justification Encl

ML20127G917
Person / Time
Site:	Fermi
Issue date:	06/21/1985
From:	DETROIT EDISON CO.
To:
Shared Package
ML20127G914	List: ML20127G910 ML20127G917
References
NUDOCS 8506260137
Download: ML20127G917 (18)

Text

_ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ - . __. _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ __ _- -__

Attachment 1 Pronosed Chanacs to the Fermi 2 Technical Snecifications Pages attached: 3/4 3-44 3/4 3-00 6-1 6-2 6-3 6-4 6-6 with new incert 6-7 6-0 6-9 6-14 62gog [ffh* 1 P

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car may be rcAuced += o.7 c yc Prodded no cip.\_t._m y is 1 2.

l rdia 1ABLE 3.3.6-2 l

l CONTROL ROD bt0CK INSTRUMENTATION SETPOINTS A ALLOWABLE VALUE 5 TRIP FUNCTION TRIP SETPOINT

. 1. ROD BLOCK MONITOR Upscale < 0.66 W + 40%* < 0.66 W + 43%*

l E a.

NA O b. Inoperative RA

> 5Y of RATED TIIERMAL POWER > 3% of RATED THERMAL POWER

~ c. Downscale l 2. APRM

a. Flow Biased Neutron Flux - High 5 0.66 W + 42%* < 0.66 W + 45%*

NA

b. Inoperative NA

> 5% of RATED THERMAL POWER > 3% of RATED THERMAL POWER

c. Downscale

d. Neutron Flux - Upscale, Setdown 512%ofRATEDTHERMALPOWER {14%ofRATEDTHERMALPOWER

3. 50tfRCE RANGE MONITORS NA

a. Detector not full in MA

< 1.6 x 105 cps

b. Upscale < 1.0 x 105 cps w c. Inoperative NA a NA gg

> 3 cps > 2 cps i d. Downscale Y 4 INTERPEDIATE RANGE MONITORS NA

a. Detector not full in NA

< 110/125 divisions of

b. Upscale < 108/125 divisions of .

Tull scale Tull scale l NA

c. Inoperative NA l

d. Downscale > 5/125 divisions of > 3/125 divisions of Tull scale l

ull scale

5. SCRAM DISCHARGE VOLUME ,

1. ~

a. Water Level-High <. m... _ S I? 'll 2 < T .,A M S?/ O i NA

~

b. Scram Trip Bypass NA

6. REACTOR COOLANT SYSTEM RECIRCULATION FLOW

a. Upscale $ 108/125% of rated flow $ 111/125% of rated flow NA NA l b. Inoperative

c. Comparator 3 10% flow deviation i 11% flow deviation NA NA 7

7. REACTOR MODE SWITCH SHUTDOWN POSITION l

• The rod blocit function is varied as a function of recirculation loop drive flow (W). The trip setting l of this function must be maintained in accordance with Specification 3.2.2.

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.' I TABLE 3.3.7.12-1 (Continued)

^

TABLE NOTATIONS

• At all times. - .

• • During main condenser offgas treatment system operation.

• • • 0uring operation of the train condenser air ejector. 4

1. During operation of the standby gas trestment system.

ACTION STATEMENTS ACTION 121 - With the number of channels CPERABLE less than required by the Mriimcm Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

That wdhin 9 hows ACTION 122 - With the number of channnels OPERABLE one less than required by the Miriimum Channels OPERABLE requirement, effluent release via this pathway may continue for up to 30 days provided amples are cc,ntinuously collected with auxiliary sampling equipment as s

required in Table 4.11.2.1.2 1.

ACTION 123 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via a this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 124 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of main condenser offgas treatment system may continue for up to 30 days provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 125 - With the number of channels OPERABLE less than required by the

! Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

, ACTION 126 - With the number of channels OPERABLE less than required by the i

Minimum Channels OPERABLE requirer.ent, releases via this pathway l

to the envir.onment may contim.e' for up to 7 days provided that:

l

a. Thesaffgas system is not bypassed, and

b. The reactor building exhaust plenum noble gas effluent-(downstream) monitor is OPERABLE; Otherwise, be is at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. )

i- FERMI - UNIT 2 3/4 3-80 J

e 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY Assisia d N Awa f .,

6.1.1 The E;r '-t: int-Nuclear Production shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Nuclear Shif t 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 Vice President-Nuclear Operations shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION . .

OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2.1-1.

UNIT STAFF 6.2.2 The unit organization shall be as shown on Figure 6.2.2-1 and:

a. Each on duty shift shall be composed of at least the minimum shift h crew composition shown in Table 6.2.2-1;

b. At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Operator shall be in the control room;

c. A Health Physics Technician

• shall be on site when fuel is in the reactor;

d. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation;

e. A site fire brigade of at least five members shall be maintained on site at all times *. The fire brigade shall not include the Nuclear Shift Supervisor, the Shift Technical Advisor, nor the two other .

members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency; and

The Health Physics Technician and fire brigade composition may be less than

• the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

')

FERMI - UNIT 2 6-1

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued)

f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (e.g., licensed Senior Operators, licensed Operators, health physicists, auxiliary operators, and key maintenance 1 personnel).

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the unit is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended perinds of shut-down for refueling, major maintenance, on major unit modifications, on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all excluding shift turnover time.

A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work i

3.

periods, including shift turnover time.

j 4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the l  ;;;r'9t:nd;nt-Nuclear Production or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by th- C;;;r'.t;;d;nt-Nuclear Production or his designee to assure tha excessive hours have not been ~

I assigned. Routine deviation rom the above guidelines is not f authorized.

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, 6.2.4 SHIFT TECHNICAL ADVISOR l

l 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support I to the Nuclear Shift Supervisor in the areas of thermal hydraulics, reactot_

' engineering, and plant analysis with regard to safe operation of the unit. The l .

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(

! *Not responsible for sign-off function.

FERMI - UNIT 2 6-6

6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

PUNCTION 6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other cources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving unit safety.

COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five dedicated, full-time engineers located onsite, each with a bachelor's degree in engineering or related science and at least two years professional level experience in his field.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance,of unit activities to provide independent verification that these activities are performed correctly and that human errors are reduced as much as practical.

AUTHORITY

~6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving unit safety to the Assistant Manager-Regulation and Compliance.

i

ADMINISTRATIVE CONTROLS [

SHIFT TECHNICAL ADVISOR (Continued)

Shif t Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and

! controls in the control room.

6.3 UNIT STAFF QUALIFICATIONS ggggn \ $vptvv{5er -

6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable positions, except for Health Physics 5;;; n i;;r who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed Operators and Senior Operators shall also meet or exceed the minimum ~ qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 29, 1980 NRC letter to all licensees.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Director, Nuclear Training., shall meet or exceed the requirements and recommendations of Section 5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 29, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.

6.5 REVIEW AND AUDIT 6.5.1 Onsite Review Organization (OSRO)

FUNCTION 6.5.1.1 The OSR0 shall function to advise the 5 4;r'nt--dat-Nuclear Production on all matters related to nuclear safety.

f COMPOSITION 455$5bwk MW9 #Y 6.5.1.2 The OSR0 shall be composed of the:

Chairman Sup: 'nt; Jm,J.-Nuclear Production .

• • 5 Vice-Chairman t:':t;-t Superintendent-L;l;;. Iced ; tier.0PS 6esead Vice-Chairman ^rrict:nt te Superintendent ".;;;.. Ic.J,.;;ien Ddfr "'rd "!;s O .! m:a Operations Engineer S :i;t;nt Op;r; tier.; Engi.n r 0;;, .t;. .,

Member Technical Engineer Member Maintenance Engineer Member Radiation Protection-Chemical Engineer Member Supervisor Operational Assurance Member Reactor Engineer

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FERMI - UNIT 2 6-7

k ADMINISTRATIVE CONTROLS  !

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the OSR0 Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in OSR0 activities at any one time.

MEETING FREQUENCY 6.5.1.4 The OSRO shall meet at least once per calendar month and as convened by the OSRO Chairman or his designated alternate.

I QUORUM

6. 5.1. 5 The quorunt of the OSR0 necessary for.the performance of the OSR0 responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and"4+we members including ofTo Two alternates. Sour RESPONSIBILITIES

6. 5.1. 6 The OSR0 shall be responsible for:

a. Review of (1) all procedures required by Specification 6.8 and changes thereto, (2) all programs required by Specification 6.8 and changes thereto, and (3) any other procedures or changes thereto as determined by the S w intad:nt-Nuclear Production to affect nuclear safety; kSSiSM M&nagtv-

b. Review of all proposed tests and experiments that affect nuclear safety;

c. Review of all proposed changes to Appendix A Technical Specifications;

d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety; -

e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the Manager-Nuclear Operations and to the Nuclear Safety Review Group;

f. Review of all REPORTABLE EVENTS;

g. Review of unit operations to detect potential hazards to nuclear safety; ,

h. Performance of special reviews, investigations, or analyses and reports l thereon as requested by the Lp;rint xdn t-Nuclear Production or the Nuclear Safety Review Group; Assidawt f%e$te _

i. Review of the Security Plan and implementing procedures;?"d ""hai++21

f rxxxxd:d :hr;;n t: th: " :l =r Of:t3 " . in C, y, J. Review of the Emergency Plan and implementing procedures;rd :d-itta'

f::x: xd:d 1..;x :: t': "r ! =- O f: t; ": i n C r-T ;

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FERMI - UNIT 2 6-8 s

ADMINISTRATIVE CONTROLS

( I RESPONSIBILITIES (Continued)

k. Review of any accidental, unplanned or uncontrolled radioactive release including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Vice President-Nuclear Operations and to the Nuclear Safety Review Group; and Review of changes to the PROCESS CONTROL PROGRAM and the DFFSITE  !

1.

l DOSE CALCULATION MANUAL.

6.5.1.7 The OSR0 shall: g;,qj jyIAna.$Cr l

a. Recommend in writing to the 4. ...t;c.d;;t-Nuclear Production approval or disapproval of items considered under Specification 6.5.1.6a. l through d. prior to their implementation.

b. Render determinations in writing to the Nuclear Safety Review Group with regard to whether or not each item considered under Specifica-tion 6.5.1.6a. through e, constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Manager-Nuclear Operations and the Nuclear Safety Review Group of disagreement between the OSRO and the ' p. i..;;r.dat-Nuclear Production; however, the M : 'nt:g_...t-Nuclea3 Production shall have responsibility for resolution ofi such rdisagreements pursuant to Specification 6.1.1.

( RECORDS 6.5.1.8 The OSR0 shall maintain written minutes of each OSR0 meeting that, at a minimum, document the results of all OSR0 activities performed under the responsibility provisions of these Technical Specifications. Copies shall be provided to the Hanager-Nuclear Operations and the Nuclear Safety Review Group. _

6.5.2 NUCLEAR SAFETY REVIEW GROUP (NSRG)

FUNCTION 6.5.2.1 The NSRG shall function to provide independent review and audit of designated activities in the areas of:

a. Nuclear power plant operations,

b. Nuclear engineering,

c. Chemistry and radiochemistry. -

d. Metallurgy,

e. Instrumentation and control,

f. Radiological safety,

g. Mechanical and electrical engineering, and -

• h. Quality assurance practices.

i The NSRG shall report to and advise the Vice President-Nuclear Operations on those areas of responsibility in Specifications 6.5.2.7 and 6.5.2.8.

FERMI - UNIT 2 6-9

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Cortinued) gghf gg 6.8.2 EachprocedureofSpecification6.8.1,andchangeskthereto,shallbe reviewed by the OSRO and shall be approved by the Q ;.:..;;.-i nt-Nuclear Production prior to implementation and reviewed periodically as set forth in administrative procedures. .

6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:

a. The intent of the original procedure is not altered; ,

b. The change is approved by two members of the unit management staff,  :

at least.one of whom holds a Senior. Operator license on Fermi 2; and

c. The change is documented, reviewed by the OSRO, and approved by the ic' Audik;wi b.-.t-Nuclear vager Production within 14 days of implementation.

6.8.4 The following programs shall be established, implemented, and maintained:

1

a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the HPCI, CS, RHR, RCIC, reactor water sampling, containment sampling, reactor water cleanup, combustit;ie gas control, control rod drive discharge headers, and standby gas treatment systems. The program shall include the following:

1. Preventive maintenance and periodic visual inspection requirements, and

2. Integrated leak test requirements for each system at refueling cycle intervals or less.

b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident -

conditions. This program shall include the following:

l

1. Training of personnel, _

l l 2. Procedures for monitoring, and l 3. Provisions for maintenance of sampling and analysis equipment.

c. Post-accident Sampling * .

l

, A program which will ensure the capability to obtain and analyze 7eactor l coolant, radioactive iodines and particulates in plant gaseous efflu-l ents, and containment atmosphere samples under accident conditions. ,

1

*Not required until prior to exceeding 5% of RATED THERMAL POWER.

! FERMI - UNIT 2 6-14

Attachoent 2 Justification for Proposed Changes to Fermi 2 Technical Specifications Table 3.3.6-2, item 3 (nace 3/4 3-44)

The proposed change allows the rod block setpoint to be reduced in the event that the incore neutron strength drops below 3 cps as could occur during a prolonged outage. As long as the signal-to-noise ratio is 1 2 sufficient signal strength is available for proper SRM operation. This also makes this Tech Spec consistent with the SRM Tech Spec Surveillance requirements 4.9.2.c and 4.3.7.6.c and has been accepted on other dockets.

Table 3.3.6-2, item 5 (nace 3/4 3-44)

See Reference (2) for justification.

Table 3.3.7.12-1 (nace 3/4 3-80)

The proposed change clarifies that the auxiliary sampling equipment must be in place within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the channel is declared inoperable. This is consistent with the allowance of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to obtain a grab sample in Action Statement 121.

Section 6.1 (nace 6-1)

The title " Superintendent-Nuclear Production" now becomes

" Assistant Manager-Nuclear Production" as part of an organizational change to strengthen the role of the individual directly responsible for unit operation within the Detroit Edison Nuclear Operations organization. See justification statements for changes to Figures 6.2.1-1 and 6.2.2-1 for a discussion of the organization change.

Section 6.2.2.f (nace 6-2)

See justification statement for Section 6.1 above.

Piaure 6.2.1-1 (nace 6-3)

Revised offsite organization is shown as discussed with NRC Region III representatives in Glen Ellyn, June 14, 1985.

The organizational change strengthens the role of the unit management within the Nuclear Operations organizational structure by elevating the position of Plant Superintendent to an Assistant Manager level. In addition, the authority for the functions of the Project Management Organization is transferred to Nuclear Engineering and the plant organization as appropriate. Consolidation of other responsibilities is reflected in the formation of three other Assistant Manager level positions other than the one for the plant. The General Director-Nuclear Operations Services reflects combining Nuclear Training, Security, and Administration under one unit head. The Assistant Manager-Nuclear Engineering reflects combining the previous Nuclear Engineering and Project Engineering from the Construction Project Management Organization under Nuclear Operations Management. Provision is made for an Architect-Engineer to report to this unit head. The Assistant Manager-Regulation and Compliance reflects a combination of Quality Assurance, Licensing, the Independent Nuclear Safety Review and the Independent Safety Engineering Group activities under one unit head. Detroit Edison believes that consolidation of these activities in this mann:r will increase significantly the visibility and effectiveness of these functions within Nuclear Operations. Moving the Independent Safety Engineering activity out from Nuclear Engineering requires restructuring of the Independent Safety Engineering Group (ISEG) to the more traditional scheme (see modification to Technical Specification 6.2.3).

Piaure 6.2.2-1 (pace 6-4)

As stated previously, the unit organization is being strengthened by elevating the position of Superintendent to an Assistant Manager plus combining under his authority functions which deal with plant modifications and Outage Management. This latter item increases the responsibility of the previous Maintenance Engineer and thus elevates his position to a Superintendent level.

Section 6.2.3 (pace 6-6)

As stated in the justification for changes to Figure 6.2.1-1, the Independent Safety Engineering Group (ISEG) functions were transferred under the authority of the new Assistant Manager-Regulation and Compliance. This requires restructuring the ISEG to an organization like ones previously accepted by the NRC staff at other plants and as is documented in Standard Technical Specifications.

Section 6.3 (pace 6-7)

Title change only reflective of the revised organization.

Section 6.5..l.1 (nage 6-7)

Title change reflective of the revised organization. See justifications under Section 6.1, Figures 6.2.1-1, and Figure 6.2.2-1.

Section 6.5.1.2 (nace 6-7)

Title changes in right hand column are reflective of the revised organization. See justifications under Section 6.1, Figure 6.2.1-1, and Figure 6.2.2-1. Deletions and changes to the left hand column were previously submitted and justified in Reference (2).

Section 6.5.1.5 (nace 6-8)

Previously submitted with Reference (2).

Section 6.5.1.6a and h (nace 6-8)

Title changes reflective of revised organization. See justifications under Section 6.1, Figure 6.2.1-1, and Figure 6.2.2-1.

Section 6.5.1.6i and i (nace 6-8)

Previously submitted with Reference (2).

Section 6.5.1.7a and c (paae 6-9)

Title changes reflective of revised organization. See

-justifications under Section 6.1, Figure 6.2.1-1, and Figure 6.2.2-1.

Section 6.8.2 and 6.8.3 (cace 6-14)

Title changes reflective of revised organization. See justifications under Section 6.1, Figure 6.2.1-1, and Figure 6.2.2-1.