ML20235V025
| ML20235V025 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/08/1987 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20235V023 | List: |
| References | |
| NUDOCS 8710140454 | |
| Download: ML20235V025 (13) | |
Text
{{#Wiki_filter:.'
. . /, .
l 1
~
SECTION 6.0 ADMINISTRATIVE CONTROLS
- k. ,. .
e 8710140454 871000' PDR ADOCK 05000458 P PDR
..i.,_ .
ADMINISTRATE. fiOLS UNIT STAFF (Or- . u.e d )
- f. Administrative procedures shall be developed and implemented to limit the working hours of unit staf f who perform safety-related functions, l (e.g. , licensed Senior Operators, licensed Operators, radiation pro- I tection technicians, auxiliary operators, and key maintenance i personnel).
Adequate' shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a nominal 42-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 periods of shutdown for refuel- t ing, major' maintenance, or 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 hours straight, excluding shift turnover time.
- 2. An individual'should not be permitted to work more than 16 hours -{
in any 24-hour period, nor more than 24 hours in any 48-hour period, nor more than 72 hours in any seven day period, all excluding shift turnover time.
- 3. A break of at least eight hours should be, allowed between work periods,_ including shift turnover time. l
- 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 Plant Manager or either one of the Assistant Plant Managers or the
-l Director l + Sprei=-Radiological Programs, or higher levels of management, in l 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 the Plant Manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.
l l l RIVER BEND - UNIT 1 6-2
... e.
l DELETE' i 3 m.assaman 81 set 1 1 948 MhtWNert i
==*
l I l inama a 98 CT Lf77 no6 us I \ E Ct uti Am
.IRf.CT.,A
. ter m.vieu g g West #etWDe.ut aa*
c
.4.Ff.t1 am a
I E mm.8.
.,a,8 E,, .u ton M M 88"#.88887AA g g M JECT.
. . P6am,an.a.g
.. C
.artTv.t.s.Sie.sttaisee
\ E Dvie ww.
Saama a pe0Jtet. Sm.aut t a *6 CLEAR g FW6t4&m0 ue 1 m
/ u a e, u
" **=*===t -
te, ter. arma
.mu in.,.Cou.
meta, a um /w.eun a.na n 4 c urm amm unoma
\,
a a a.te.su
. .e
=*w. e.ev.
=.,=, =
I gammt., alatattom em m ,1 tes.se. l a E
*"'***" i t
W E E . l-I suMCT.e pp I l cuarty awa gate.ttu.CV
.u . .mu.c.A.a.an watemat.
.su I -
FIGURE 6.2.1 1 R8NG ORGANIZATION 1 RIVER BEND - UNIT 1 6-3 )
1 l CHAIRMAN OF mE BOARD SENIOR MCE PRESIDENT RBNG I M 1 MANAER - MANAGER PLANT
=
MANAGER MANAGER RIVER BEND PROJECT - _ _ MANAGER ENQNEERING ADMINISTRATION OVERSIGHT - MANAGEMENT l
, I SUPERVISOR l SUPERVISOR INDEPENDENT DIRECTOR DIRECTOR DIRECTOR SAFETY RIVER BEND -
MANAGEMENT l - ENQNEERING - NUCLEAR . ENQNEERING PROJECTS SYSTEMS l ADMINISTRATION TRAINING GROUP 8 l l DIRECTOR ' DIRECTOR SUPERVISOR SUPERVISOR l ENQNEERING EMERGENCY PLANT MATERIALS - - OVERSIGHT . MANAGEMENT l ANALYSIS PLANNING l l OUTAE SUP SOR R
-- U _ _
NU UCENSING MANAER ,g ST Tl I I MANAER SUPERVISOR DIRECTOR SUPERVISOR QUALITY PLANNING & l - - ADMINISTRATIVE DESIGN ASSURANCE SCHEDUUNG l ENQNEERING SERVICES l l l SUPERVISOR SUPERVISOR - DIRECTOR gg SERMCES NUCLEAR FUELS L_ FIELD ENQNEERING ENVIRONMENTAL SERVICES DIRECTOR
---- *PMs oMnisMWy to me MonogMnginMng, but is responsible for day-to-day engineering support OERMS f the plant.
QA FIGURE 6.2.1-1 RIVER BEND STATION ORGA~NIZATION RIVER BEND - UNIT 1 6-3
, c ;
w.
!b ,
d
.,,4
'l 1
DELETE <' mwr samaeta SfuTIL teMuthCa&L setaat:0m om6te E
- I 1 9 I I am*'** =5 ,.,6, ,,,6,,- av.0 su eaa460 A.Opta4Te0mg esamaeta tt 6 AA0iOL00 SCAL Stam7pr e #'"'OI0 0 808veC4 95694Ad85 .
E*" habe4878 6 Cette4 Tat TEST
~.
E
- I J t
'r osatans 8d '
94 tape 879V getaAfD0e8 M# 6 avetoa , gyptovsom l / -
.,.., ', r getA&ftesel .. j
*'f' gyptav60s J V . t e.n - .
e,n TecusstCAL stav6046 ! A9v50m
~
/ 1 7....................,, y m ........----.3 1
..,8 e va06 \, 'g,0,n auC6ame nasiaten AAf*G gggns
- teussutut l I be em0fttftces gpeasfems TOCsemecaant 04teetti :
l* .. t ,.We.g.u v.0s, auctua geeftm0L l l PG Ass 0 C0esTROLS
)
T00seseCaaut 8'8#'T888
/ I
- . .t._., t.
a T88'" engastent I , 1
/pganaammiemage To start Tse 9 W SAsGAS$
...as toest es08vigue&4 AAG tu eserf enff te 1101989001 DIAtttt? TO TuS $ sept gypteveDe penLrsgs est agentMats test etwee ashassef ullut tai titt
- Test part ?$ CseapC AL A0v408 IST&l P0sittee N AT bt 96LL3 0 Sv he On eseIPT Ssert 1 egetav60e OA C0stTD06 OPE haimG f estasas pa0 vets test enkvspunk settTS 998 314.GuaLaPICAta0ed
.m .n D8 Detts8tCaficer &J d assD 6 8 are**8n uttrvtDe&&4 emt Tea &&asstatteel est? $sIDett FIGURE 6.2J 1 RIVER DEND STATION ORGANIZATION '
RIVER BEND - UNIT 1 6-4
PLANT MANAGER e
+ +'
ASSISTANT : ESISTANT ASSISTANT PLANT PLANT PLANT DIRECTOR MANAGER MANAGER MANAGER RADIOLOGICAL MAINTENANCE OPERATONS AND "rECHNICAL PROGRAMS RA! WASTE j i SERVICES NRmi
~_.
g
+ -
+ 1 RADWASTE SUPERVISOR REACTOR OPERATlONS - OtEMISTRY ADMINISTRATIVE ENQNEERING SUPERVISOR SUPERVISOR SUPERVISOR SERMCES SUPERMSOR guennunu ASSISTANT OPERATIONS SUPERVISOR >
SHIFT EGNM + SUP SORS E ADVISOR .- q I l - l RADIATION < CONWnt RADWASTE SHIF",, i NUCLEAR PROTECTION OPERATING F- TECHNIQANS FOREMAN CLERK EQUIPMENT OPERATORS g - l INSTRUMENTATION - - TH(SE INDIVIDUALS ARE ON SHIFT, BUT DO NUCLEAR L.- CON M M AND CONEOL NOT REPORT DIRECTLY TO THE SHIFT SUPV. UNLESS HE REPRESENTS THE SENIOR MANAGE-TECHNIQANS OPERATORS l MENT ON SITE. l ' " " "' ' ' ' " '
- THE SHIFT TECHNICAL ADVISOR (STA) POSITION MAY BE RLLED BY AN ON-SHIFT SHIFT SUPV.
l ,O OR CONTROL OPERATING FOREMAN PROVIDED NUCLEAR ; THE INDIVIDUAL MEETS THE STA QUAURCATIONS l *E"'8 Y EQUIPMENT OF SPEClRCATION 6.2.4 AND 5 UCENSED r- gCHNl0 M OPERATORS INDIVIDUALS ARE ON SHIFT. l immuumusumunumunu h ORGANIZATION NOT SHOWN. NON-OPERATIONS ! l PERSONNEL FIGURE 6.2.2-1 ((TH
~
RIVER BEND STATION ORGANIZATION RRE DRICADE quumummmmmmmmmmmu RIVER BEND - UNIT 1 6-4 L . _ _ . - _________._____ _ _ _ _ _
C . l ADMINISTRATIVE CONTROLS L
~ 6. 2. 3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)
FUNCTION 6.2.3.1 The .ISEG shall function to examine unit operating characteristics, NEC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of simi-lar design, which may indicate areas for improving unit safety. The ISEG shall j
'make detailed recommendations for revised procedures, equipment modifications, -
maintenance activities, operations activities, or other means of improving unit )
-safety to Cne Vice .^re;idst R f;t3 a d D .ir= x at.: l.
l COMPOSITION l Manager-River Bend Oversight!
-6.2.3.2 The ISEG sha11 be composed of at least five, dedicated, full-time engineers-located onsite. Each shall have a bachelor's degree in engineering
'or related science and at least 2 years professional level experience in his field, of which at least 1 year experience shall be in the nuclear 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 per-formed correctly'and that human errors are reduced as much as practical.
RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to the,'Vi;; "rn'd;nt - Of;t; =d O sir; :.nt. IManager-River Bend Oversight l 6.2.4 SHIFT TECHNICAL ADVISOR [ded i cated f-- 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit. The* Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineer-ing 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. For the dual _ role position shown in Table 6.2.2-1, the Snift Technical Advisor ; shall have a bachelor's degreeter ;h:11 hs; apleted ;11 t;;hni;:1 :=r;;; l r;;ir:d nr th; d;;rn 'r : ;;intifi: ;r = ; h u r'n; d h;fplin; and shall have received all of the training for the normal STA position described above. in engineering, engineering technology, or a physical science from an accredited institution, including course work in the mathematical or engineering sciences,
,_. or e professional engineer's license
*Not responsible for sign-off function. obtained by successful completion of the PE examination RIVER BEND - UNIT 1 6-6
..,, .~
i ADMINISTRATIVE CONTROLS
~ 6. 3 UNIT STAFF OVALIFICATIONS IDIrector: {
l 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica- j tions of ANSI /ANS 3.1-1978 for comparable positions, except for the*C g;rvi;;r- l 1 Radiological Programs who shall meet or exceed the qualifications of Regulatory l 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 28, 1980 NRC letter to all licensees. , 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall i be maintained under the direction of the Director - Nuclear Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI / ANS 3.1-1978 and Appendix A of 10 CFR Part 55 and the supplemental requirements { specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter 1 to all licensees, and shall include familiarization with relevant industry operational experience. 6.5 REVIEW AND AUDIT 6.5.1 FACILITY REVIEW COMMITTEE (FRC) FUNCTION 6.5.1.1 The FRC shall function to advise the Plant Manager on all matters related to nuclear safety. COMPOSITION , 6.5.1.2 The FRC shall be composed of the: Chairman: Assistant Plant Manager-Technical Services byd Radwest el Member: Assistant Plant Manager-0perationsf;ed ene end Ct.;;f;trf Member: Assistant Plant Manager-Maintenance 2nd ".:t:rSi Member: Operations Supervisor Member: C g:r; h:r! radiological R Program loirectori l' Member: Reactor Engineering Supervisor Member: Control Systems Supervisor Nember: Chemistry Supervisor] ALTERNATES IMember: Process systems supervisors f.5.1.3 All alternate members shall be appointed in writing by the FRC Chairman 3 to serve on a temporary basis; however, no more than two alternates shall partici-pate as voting members in FRC activities at any one time. L MEETING FREQUENCY 6.5.1.4 The FRC shall meet at least once per calendar month and as convened by the FRC Chairman or his designated alternate. RIVER BEb!D - UNIT 1 6-7
.,i .
' ADMINISTRATIVE CONTROLS 000 RUM 6.5.1.5 The quorum of the FRC necessary for the performance of the FRC responsibility and authority provisions of these Technical Specifications shall I consist of the Chairman or his designated alternate and four members including no more than two alternates.
RESPONSIBILITIES 6.5.1.6 The FRC shall be responsible for:
- a. Review of all plant general administrative procedures and changes thereto;
- 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 structures, compo-nents, 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 Vice n President - R8NG l i
and the Nuclear Review Board; 15eniori
- f. Review of all REPORTABLE EVENTS;
- g. Review of unit operations to detect potential hazards to nuclear safety; items that may be included in this review are NRC inspection reports that require written response, QA audits / surveillance findings of operating and maintenance activities, NRB audit results, and Ameri-can Nuclear Insurer (ANI) inspection results;
- h. Performance of special reviews, investigations, or analyses and reports ,
thereon as requested by the Plant Manager or the Nuclear Review Board; l
- 1. Review of initial start-up testing phase start-up procedures and revisions; and
- j. Review of the Emergency Plan and implementation procedures at least once per 12 months and all proposed changes thereto.
I 6.5.1.7 The FRC shall:
- a. Recommend in writing to the Plant Manager approval or disapproval of items considered under Specification 6.5.1.6.a. through d. prior to their implementation,
- b. Render determinations in writing with regard to whether or not each ,
item considered under Specification 6.5.1.6.a. through e. constitutes an unreviewed safety question. henios
- c. Provide written notification within 24 hours to the(Vice President - l RBNG and the Nuclear Review Board of disagreement between the FRC and the Plant Manager; however, the Plant Manager shall have respon- l sibility for resolution of such disagreements pursuant to Specifica-tion 6.1.1.
RIVER BEND - UNIT 1 6-8
-ADMINISTRATIVE CONTRDLS RECORDS 6.5.1.8 The FRC shall maintain written minutes of each FRC meeting that, at a minimum, document the results of all FRC activities performed under the respon-sibility provisions of these Technical specifications. Copies shall be provided to the Plant Manager and the NRB.
6.5.2 TECHNICAL REVIEW AND CONTRDL 6.5.2.1 Each procedure and program required by Specification 6.8 and other pro-cedures that' affect nuclear safety, and changes thereto, is prepared by a quali-fled individual / organization. Each such procedure, and changes thereto, shall be reviewed by an individual / group other than the individual / group that pre-pared the procedure, or changes thereto, but who may be from the same organiza-tion as the individual / group that prepared the procedure. Each such procedure and program, or changes thereto, shall be approved, prior to implementation, by the Plant Manager or one of the Assistant Plant Managers or the S;:r : r - *- Radiological Programs, with the exception of the Emergency Plan and implement- ll ing procedures which shall be approved by the Manager - Administration, Plant Manager andg Vice President - RBNG. l 15eniorl ID i recton, 6.5.2.2 Individuals responsible for reviews performed in accordance with Sec-tion 6.5.2.1 shall be members of River Bend Nuclear Group supervisory staff, and the reviews shall be performed in accordance with administrative procedures. Each such review shall include a determination of whether or not additional, cross-disciplinary review is necessary and a verification that the proposed actions do not constitute an unreviewed safety question. If deemed necessary, ) such review shall be performed by the appropriate designated review personnel. 6.5.2.3 The station security program and implementing procedures shall be reviewed at least once per 12 months, and recommended changes approved in ac-cordance with Specification 6.5.2.1. 6.5.2.4 The station emergency plan and implementing procedures and recommended l changes shall be approved in accordance with Specification 6.5.2.1.
- 6. 5. 2. 5 The station fire protection plan and implementing procedures shall be reviewed at least once per 12 months, and recommended changes approved in accordance with Specification 6.5.2.1.
6.5.2.6 Records documenting each of the activities performed under specifica-tions 6.5.2.1 through 6.5.2.5 shall be maintained. 6.5.3 NUCLEAR REVIEW BOARD (NRB) FUNCTION l l 6.5.3.1 The NRB shall funct M to provide independent review and audit of designated activities in the areas of: l l RIVER BEND - UNIT 1 6-9
,,8, .
ADMINISTRATIVE CONTROLS FUNCTION (Continued)
- 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,
- h. Quality assurance practices,
- 1. Licensing and regulatory affairs,
- j. Training.
The NRB shall report to and advise the Senior Vice President - RBNG on those areas of responsibility in Specifications 6.5.3.7 and 6.5.3.8. COMPOSITION 6.5.3.2 The NRB shall be composed of the: [ Manager-River Bend Oversighti g Chairman: ^!! n "r;;id;nt - a f;;. a d Erv'rn : n ; Member and Vice '.'i n P r a ; i d e n ; =N; 1 Manager-ouality Assurancel Chairman N Member: Manager - Administration Member: O n . t i . ; " !; ; r , ; ; ! d e n t L ti ... 1 A f f e i. . ...; 7. . d ;. ... l Member: Manager-Design Engineering. l Technical Services Department Member: Mn;; r- En; inn 7'n;, '!=1n T.;;;, nd '. inn;ing V -{ Manager-Engineering l Member: Plant Manager bnd Radwa stel Member: Assistant Plant Manager-0perations feT ,edu;;; en: ' " Che;; ';t. 7 A Member: Mn_;;r ^= lit; '.M arZC l Member: Director-Nuclear Licensing [ Director-Design Engineering] Member: Oiruter *:alnr Pint l
, inginn ring M Outage Manager) 44embee: Oir^.;t;r ".;l n r I Zl; h fir.
nd % Nt; .".ZI,,;I; IHember: Director-Joint Ownership Participation l , l Member: Director-Pient Oversight l 6.5.3.3 All alternate members shall be appointed in writing by the NR8 Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NRB activities at any one time. CONSULTANTS 6.5.3.4 Consultants shall be utilized as determined by the NRB Chaiman to provide expert advice to the NRB. RIVER SEND - UNIT 1 6-10
.. l .
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) l
- 2. Integrated leak test requirements for each system, at refueling cycle intervals or more frequently.
- b. In-Plant Radiation Monitorino 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:
- 1. Training of personnel,
- 2. Procedures for monitoring, and
- 3. Provisions for maintenance of sampling and analysis equipment.
- c. Post-accident Samplina l
A program which will ensure the capability to obtain and analyze , reactor coolant, radioactive iodines and particulate in plant j gaseous effluents and containment atmosphere samples, under accident conditions. The program shall include the following:
- 1. Training of persennel,
- 2. Procedures for sampling and analysis, and
- 3. Provisions for maintenance of sampling and analysis equipment.
- d. Biofoulina Prevention and Detection A program, approved by the NRC Staff prior to introduction of river ;
water to the systems, which will include the procedures to prevent l biofouling of safety-related equipment, to assure detection of Corbicula in the intake embayment and the Mississippi River at the River Bent Station site, and to monitor and survey safety-related equipment to de-tect biofouling. Changes to this program will be submitted to and approved by the NRC (both the Region and NRR) prior to implementation. 6.9 REPORTING REQUIREMENTS U. 5. Nuclear Regulatory Commission, Document Control Desk, Washington, DC 20555, with a copy to ROUTINE REPORTS the Regional Office of the NRC and a copy to the
- NRC Resident Inspector.
6.9.1 In addition to the app 1' cable reportirg requirements of Title 10, code of Federal Regulations, the following reports shall be submitted to the Av.aini;tr;ter ;f th; 0;;t;n;1 Offic; ef the %20 unless otherwise noted.ggi;n;; , l STARTUP REPORT 6.9.1.1 A summary report of plant startup and power eseslation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to RIVER BEND - UNIT 1 6-15
I l
\
l l ADMINISTRATIVE CONTROLS SEMIANNUAL EFFLUENT RELEASE REPORT (Continued) to MEMBERS OF THE PUBLIC due to their activities inside the SITE 80VNDe l (Figure 5.L3) during the report period. All assumptions used in making tb6e ! assessments (i.e., specific activity, exposure time and location) shall be in- l cluded in thers reports. The assessment of radiation doses shall be performed j in accordance with the methodology and parameters of the OFFSITE DOSE CALCULA- l TION MANUAL (ODCM). j The Semiannual Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most-exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power ! Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977. The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period. The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the ODCH, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specifi-cation 3.12.2 U. 5. Nuclear Regulatory Commission, Document Control Desk, SPECIAL REPORTS Washington, DC 20555, with a copy to the Regional Office of the NRC and a copy to the NRC Resident Inspector, 6.9.2 Special reports shall be subm';,ted in the following manner:
- a. Specialreportsshallbesubmittedtothek;;'en;lfiini;tret;;;f tM ":;i; =1 Cffi;; ef the Z C within the time period specified for each report.
- b. Special reports in regard to Corbicula will be submitted to the NRC ,
within 30 days of identification of infestation. In accordance with the settlement agreement dated October 10, 1984, these reports shall describe the level of infestation, affected systems and measures taken to prevent further infestation. 6.10 RECORD RETENTION 6.10,1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated. 6.10.2 The following records shall be retained for at least 5 years:
- a. Records and logs of unit operation covering time interval at each power level.
l t RIVER BEND - UNIT 1 6-19 _ _ _ _--}}