ML20002A440
| ML20002A440 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/25/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20002A436 | List: |
| References | |
| NUDOCS 8011170202 | |
| Download: ML20002A440 (34) | |
Text
J
- g
n::- ::::
O INDEX NE LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS E
IA SECTION Page 3/4.2 POWER DISTRIBUTION LIMITS
~~.....
- s 3/4.2.1 PEAK LINEAR HEAT GENERATION RATE.......................
3/4 2-l s
3/4.2.2 NUCLEAR HEAT FL UX HOT CHANNEL FACT 0R...................
'3/4 2-7 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR...............
3/4 2-9
- =
3/4.2.4 DNB PARAMETERS.........................................
3/4 2-11
==-
'3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE SYSTEM INSTRUMENTATION..............
3/4 3-1 J/4.3.2 ENGINEERED SAFEGUARDS SYSTEM INSTRUMENTATION...........
3/4 3-11 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...................
3/4 3-17 Incore Detection System................................
3/4 3-23 Meteorological Instrumentation.........................
3/4 3-24
~
Fire Detection Instrumentation.........................
3/4 3-27 l 3/4.4 MAIN COOLANT SYSTEM P
p =:::
3/4.4.1 MAIN COOLANT LOOPS Normal Operation.......................................
3/4 4-1 N "ef Isolated Loop..........................................
3/4 4-3 Isolated Loop Startup..................................
3/4 4-4
~
g.
3/4.4.2 SA FETY VALV ES - S HUT 60WN..',............................,
3/4 4-5 3/4.4.3 SAFETY VALVES - 0PERATING.........................'.....
3/4 4-6 3/4.4.4.' PRESSURIZER............................................
3/4 4-7.
v:
3/4.4.5 MAIN COOLANT SYSTEM LEAVAGE L_
c.
Leakage Detection Systems.
3/4 4-8 Operational Leakage....................................
3/4 4-10 YANKEE-ROWE IV i
Ja~o2 h Yo Jg
~~}:
=
l
i
(
INDEX
~~
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
=
u.y b
SECTION PAGE h
3/4.6.3 COMBUSTIBLE GAS CONTP,0L Hyd ro g e n An al yz e r..............................'........
-3/4 6-16 Hydrogen Vent System...................................
3/4 6-17
' Atmosphere Recirculation System........................
3/4 6-1.8 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Vaives.........................................;
3/4 7-1 g
Emergency Boiler Feedwater System......................
3/4 7-5 F
Primary and Deminera'lized Water Storage Tanks..........
3/4 7-6 p '::..
V:.
Activity...............................................
3/4 7-7 Eg Turbine Generator Throttle and Control Valves..........
3/4 7-9 Secondary Water Chemistry..............................
3/4 7-10 3/4.7.2 STEAMGENERATdRPRESSURE/TEMPERATURELIMITATION........
3/4 7-13 3/4.7.3 P RIMARY PUMP SE AL WATER SYSTEM.........................
3/4'7-14 3/4.7.4 SERVICE WATER SYSTEM...................................
3/4 7-16 g
3/4.7.5 CONTROL ROOM VENTILATION SYSTEM EMERGENCY SHUTDOWN.....
3/4 7-18 3/4.7.6 SEALED SOURCE CONTAMINATION............................
3/4 7-19 3/4.7.7 WASTE EFFLUENTS
~
3/4 7-21 Radioactive Solid Waste...'.............................,'
Radioactive Liquid Waste...............................
3/4 7-22 Radioactive Gaseous Wa'ste..............................
3/4 7-23.
i-3/4.7.8 ENVIRONMENTAL M0NITORING...............................
3/4 7-24 d
3/4.7.9 SHOCK SUPPRESSORS (SNUBBERS)...........................
3/4 7-27 q
b 3/4 7.10 FIRE SUPPRESSION SYSTEMS...............................
3/4 7-31 rq l
3/4 7.11 PENETRATION FIRE BARRIERS..............................
3/4 7-38 m
YANKEE-ROWE VI L
H L:
=
=
=
(
INDEX BASES SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT..................
.................. B 3/4 6-1 I
3/4.6.2 CONTAINMENT ISOLATION VALVES............................
B 3/4 6-3 F
3/4.6.3 COMBUSTIBLE GAS CONTR0L.................................
B 3/4 6-3 3/4.7 PLANT SYSTEMS
- i...
3/4.7.1 TURBINE CYCLE...........................................
B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE /TEMERATURE LIMITATION..........
B 3/4 7-4 3/4.7.3 PRIMARY PUMP SEAL WATER SYSTEM..........................
B 3/4 7-4 3/4.7.4 S E RV I CE WAT E R S YST EM.................................... B 3/4 7-4 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM EMERGENCY SHUTDOWN...... B 3/4 7-4 3/4.7.6 SEALED SOURCE CONTAMINATION.............................
B 3/4 7-4 3/4.7.7 WASTE EFFLUENTS.........................................
B 3/4 7-5 3/4.7.8 ENVIRONMENTAL MONITORING...................
B 3/4 7-6 3/4.7.9 SHOCK SUPPRESSORS (SNUBBERS)............................
B 3/4 7-6 3/4 7.10 FIRE SUPPRESSION SYSTEMS...........,....................
B 3/4 7-7 3/4.7.11 PENETRATION FIRE BARRIERS............................. B 3/4 7-7 iI I
3/4.8 ELECTRICAL POWER SYSTEMS i-3/4.8.1 A.C.
SOURCES............................................
B 3/4 8-1 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS.......................
B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REAC11VITY............................................. B 3/4 9-1 3/4.9.2 INSTRUMENTATION.........................................
B 3/4 9-1 YANKEE-ROWE XI
l'/-
in
.e -
INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE
- =.
Exclusion Area...............................................
5-1 5-1 Low Population Zone..........................................
5.2 CONTAINMENT 5-1 Configuration................................................
5-1 Design Pressure and Temperature..............................
5.3 REACTOR CORE 5-1 E
Fuel Assemblies..............................................
5-4 Control Rods.................................................
I 5.4 MAIN COOLANT SYSTEM b...
5-4 Design Pressure and Temperature..............................
5 '5 Volume.......................................................
5-4 5.5 METEOROLOGICAL TOWER LOCATI0N................................
5.6 FUEL STORAGE 5-5 C r i t i c a l i ty....................,............................
5-5 0rainage.....................................................
5-5 Capacity....................................................
5-5 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT.........................
w::=
YANKEE-ROWE XIII i
n-
~ '"
" ~ ~ '
,w--
t INDEX ADMINISTRATIVE CONTROLS PAGE SECTION 6-1 6.1 RESPONSIBILITY..........................................
6.2 ORGANIZATION 6-1 0ffsite.................................................
6-1 Facility Staff......................................
6.3 FACILITY STAFF QUALIFICATIONS...........................
6-6 6-6 6.4 TRAINING................................................
6.5 REVIEW AND AUDIT i
/
6.5.1 PLANT OPERATION REVIEW COMMITTEE Function..............................................
6-6 C om p o s i t i o n...........................................
6-7 l
6-7 A l t e r na t e s............................................
6-7 Meeting Frequency.....................................
6-7 Quorum................................................
6-7 Responsibilities.......................'...............
Authority............./.'.....:........................
6-8 Records..............................................
6-9
{
6.5.2 NUCLEAR SAFETY AUDIT AND REVIEW COMMITTEE 6-9 Func 4an..............................................
6-9 Composition...........................................
6-9 Qualification.........................................
6-10 Alternates............................................
YANKEE-ROWE XIV e
(
f_ :.
' ADMINISTRATIVE CONTROLS
=
PAGE
= is SECTION 6-10 Consultants............................................
6-10 Meeting Frequency......................................
6-10 Quorum.................................................
6-11 Review.................................................
L.m 6-11 Audits.................................................
6-12 Authority..............................................
Records................................................
6-12 e
s 6.5.3 INDEPENDENT AUDIT AND REVIEW..........................
6-12l 6.6 REPORTABLE OCCURRENCE ACTI0N...........................
6-13'l
=
6.7 SAFETY LIMIT VIOLATION.................................
6-13 6.8 PROCEDURES.............................................
6-13 e
6.9 PEPORTING REQUIREMENTS
- 6. 9.1, 6.9. 2, 6. 9. 3 R'0UTINE REP 0RTS........................
6-14 6.9.4 REPORTABLE OCCURRENCES...............................
6-17 l 6.9.5 UNIQUE REPORTING REQUIREMENTS........................
6-19
~
6.9.6 SPECIAL REP 0RTS......................................
6-22 6.10 RECORD RETENTION......................................
6-23 6.11 RADIATION PROTECTION PR'0' GRAM..'.........................
, 6-24 6.12 RESPIRATORY PROTECTION PROGRAM 6.12.1 ALLOWANCE...........................................
6-24 6.12.2 PROTECTION PR0 GRAM..................................
6-25 6.12.3 REV0 CATION..........................................
6-27 6.13 HIGH RADIATION AREA...................................
6-27 e-YANKEE-ROWE XV i
- =
k
=
s INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.4 As a minimum, the fire detection instrumentation for each ~ fire detection zone 'aown in Table 3.3.6 s'all be OPERABLE.
a APPLICABILITY.
Whenever equipment in that fire detection zone is required to be OPERABLE.
ACTION:
With the number of OPERABLE fire detection instruments less than re-quired by Table 3.3.6:
a.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, and i-b.
Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Speci-fication 6.9, prepare and submit a Special Report to the Com-
[
mission pursuant to Specification 6.9.6 within the next 30 i
days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEIL'LA"CE REQUIREMENTS 4
4.3. 3. 4 Each of the above r6 quired'.fiie detection instruments shall i
be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.
[
YANKEE-ROWE 3/4 3-27
^
i:
(
L TABLE 3.3.6 -
FIRE DETECTION INSTRUMENTS INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE 1.
Control Room' 5
2.
Cable Spreading Cable Tray House 2
Manhole No. 3 1
3.
Switchgear Room 9
4.
Diesel Generators
- No. 1
. 1 No. 2 1
No. 3 1
5.
Safety Injection Pumps and No. 3 Battery 2
t
/
YANKEE-ROWE 3/4 3-28
~
e
m.
f
(
O..g 7
PLANT SYSTEMS 3/4.7.11 FIRE SUPPRESSION SYSTEMS
~
FIRE SUPPRESSION WATER SYSTEM
.E.
o LIMITING CONDITION FOR OPERATION 3.7.11.1 ThefiresuppressionwatersystemshallbeOPERABLEwithi B =.=
a.
Two high pressure pumps, each with a capacity of 1000 gpm, with their discharge aligned to the fire suppression header, and b.
An OPERABLE flow path capable of taking suction from the Sherman Pond and transferring the water through distribution
.s piping with OPERABLE sectionalizing control.or isolation JT r=
valves to the yard hydrant curb valves.
...:
APPLICABILITY: At all times.
SE ACTION:
N
=i a.
With one pump. irioperable, restore the inoperable pump to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.9, prepare and submit a Special Report to the Cornission pursuant to Specification 6.9.6 within the next 30 days outlining the plans and procedures to be used to provide for the. loss of redundancy in this system.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
b.
With the fire suppression water system otherwise inoperable:
1.
Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 2:
Submit a Specta'l Report in accordance with Specification 6
6.9.6; I.
a)~
By ' telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b)
Confirmed by telegraph, mailgram or facsimile trans-
~
mission no later than the first working day follow-ing the event, and
.. e i
YA'iKEE-R0WE 3/4 7-31 i
s
....,.3,
.,~
c
, ~-.
PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) c)
In writing within 14 days following the event,.out-lining the action taken, the cause of the inopera-bility and the plans and schedule for restoring the system to OPERABLE status.
SURVEILLANCE REOUIREMENTS 4.7.11.1 The fire suppression water system shall be demonstrated OPERABLE-At least once per 31 days on a STAGGERED TEST BASIS by start-a.
ing each pump.
b.
At least once.per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct posit. ion.
At least once per 6 months by performance of a system flush.
c.
d.
At least once per 18 months by performing a system functional test which includes simalated automatic actuation of the system throughout its operating sequence, and:
1.
Verifying that each automatic valve in the flow path actuates to its correct position, 2.
Verifying that each pump develops at least 1000 gpm at a system head of 125 psig, t
3.
Verifying that'each,high pressure pump starts to maintain the fire suppression water system pressure 3,85 psig.
At lea' t once per 3 years by performing a flo.w test of the s
e.
system in accordance with Chapter 5, Section 11 of the Fire' Protection Handbook,14th Edition, published by the National Fire Protection Association.
YANKEE-ROWE 3/4 7-32
-*.....-4 m.
l t
FLANT SYSTEMS SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.7.11.2 The Tra~y House spray system shall be OPERABLE.
APPLICABILITY: Whenever equipment in the spray protected area is required to be OPERABLE.
ACTION:
With the above required spray system inoperable, establish a a.
continuous fire watch with backup fire suppression equipment for the unprotected area within I hour; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.6 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE0UIREMENTS The above required spray system shall be demonstrated OPERABLE:
4.7.11.2 At least once per 12 months by cycling each testable valve in a.
the flow path through at least one complete cycle of full travel.
b.
At least once per 18 months by:
Cycling.each valve in the flow path that is not testable 1.
during plant. operation through at least one complete cycle of full travel.
Inspection of the spray headers to verify their integrity, 2.
and By inspection of each nozzle to verify no blockage.
3.
At least once per 3 years by performing an air flow test c.
through each open head spray / sprinkler header and verifying each open head spray / sprinkler nozzle is unobstructed.
YANKEE-ROWE 3/4 7-33
PLANT SYSTE.S M
SYSTEM HIGH PRESSURE C0,3 LIMITING CONDITION FOR OPERATION The high pressure CO, system located in Manhole No. 3 shall be 3.7.11.3 OPERABLE with at least 90% of Yull charge weight in the main and auxiliary CO cylinders.
2 APPLICABILITY: Whenever equipment in the high pressure CO2 protected area is required to be OPERABLE.
ACTION:
With the above required high pressure C0 system inoperable, 9
-a.
establish a continuous fire watch with backup fire suppression equipment for the unprotected area within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.6 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERASLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE0UIREMENTS systems shall be demon-4.7.11.3 The above required high pressure CO2 strated OPERAELE:
cylinder weight.
At least once per 6 months by verifying CO2 a.
b.
At.least once per 18 mont.hs by:
1.
Verifying the system valves. actuate manually.
Performance of a flow test through headers and nozzles to
~
2.
assure no blockage.
YANKEE-ROWE 3/4 7-34
i PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITIONS FOR OPERATION 3.7.11.4 The following fire hose stations shall be OPERABLE:
Outside of control' room northwest door, and a.
b.
Outside of control room northeast door.
APPLICABILITY: Whenever equipment in the areas protected by the fire hose statiens is required to be OPERABLE.
ACTION:
With one or more of the above required fire hose stations a.
inoperable, route an additional equivalent capacity fire ' hose to the unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS
~
4.7.11.4 Each of the abov required fire hose stations shall be demonstrated OPEPABLE:
At least once per 31 days by visual inspection of the station a.
to assure all required equipment is at the station.
b.
At least once per 18 months by:
Removing the hose for inspection and re-racking, and 1.
Rep.lacement of all degraded gaskets in couplings.
2.
~
At least cnce per 3 years by:
c.
Fartially opening each hose station valve to verify valve 1.
OPERABILITY and no flow blockage.
Conducting a hose hydrostatic test at a pressure at least 2.
50 psig greater than the maximum pressure available at that hose station.
3/4 7-35 YANKEE-ROWE
._..,--m.
F~
PLANT SYSTEMS 3/4.7.12 PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION
.f 3.7.12 All penetration fire barriers protecting safety related areas shall be functional.
APPLICABILITY: At all times.
ACTION:
a.
With one or more of the above required penetration fire barriers non-functicnal, establish a continuous fire watch on at least one side of the affected penetration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS -
4.7.12 Each of the above required penetration fire barriers shall be verified to be functional by a visual inspection; a.
At least once per 18 months, and b.
Prior to deslaring a penetration fire barrier functional following repairs or maintenance.
\\
F
~,
/
i YANKEE-ROWE
' 3/4 7-36
~
l
.i INSTRUMENTATION BASES 3/4.3.3.2 INCORE DETECTION SYSTEM
+:
The OPERABILITY of the incore detection system with the specified minimum complement of equipment' ensures that the measurements obtained from use of this system accurately represent the reactor core power distribution. The OPERABILITY of the neutron detectors is demonstrated prior to use by irradiating each detector te be used and nomalizing their outputs.
3/4.3.3.3 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is protect the health and safety of the pubite (protective measures to required to evaluate the need for initiating and is consistent with the recomendations of Regulatory Guide 1.23, "Onsite Meteorological Pro-1 grams").
y 3/4.3.3.4 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires i
in thier early stages.
Prompt detection of fires will reduce the poten-i tial for damage to safety related equipment and is an integral element in the overall facility fire protection program.
F In the event that a portion of the fire' detection instrumentation is inoperable, the establishment of. frequent fire patrols in the affected i.
areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
- . 2 YANKEE-R0WE B 3/4 3-2
{
=
=
~
(
/
=t
=
BASES
.l 1
3/4.7.11 FIRE SUPPRESSION SYSTEMS L
The OPERABILITY of the fire suppression systems ensures triat adequate l
fire suppression capability is available to confine and extinquish fires i
occuring in any portion of the facility where safety related equipme'nt is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO, Halon and fire hose stations. The collec-2 tive capability of the fire suppression systems is adequate to minimize p
potential damage to safety related equipment and is a major element in the facility fire protection program.
In the event that portions of the fire suppression systems are inoperable, alternate backup. fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is rest.ored to service.
~
In the event the fire suppression ~ water system becomes inoperable,
}
immediate corrective mea;ures must be taken since this system provides ai==
the major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt d
evaluation of the acceptabiltty of the corrective measures to provide
~
l adequate fire suppression capability for the continued protection I
of the nuclear plant.
j 3/4.7.12 PENETRATION FIRE BARRIERS i
The functional integrity of the pentration fire barriers ensures that fires will be confined or adequately retarded from spreading to i
adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving serveral areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passibe element in the facility fire protection program and are subject to periodic inspections.
Dutrng periods of time when the barriers-are not functional, a i
continuous fire watch is requ,tred tg be maintained in the vicinity of the affected barrier until the barrier is restored to functional r
1 status.
w YANKEE-ROWE B 3/4 7-7 P
p_
t
I 6.0 ADMINISTRATIVE CONTROLS (Continued)
All CORE ALTERATIONS af ter the initial fuel loading <.nall be e.
directly supervised by either a licensed Senior Reactor if Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
A fire brigade of at least 5 members shall be maintained i.-
onsite at all times. The fire brigade shall not include the b
minimum shift crew necessary for safe shutdown of the plant, 2 members, or any personnel required for other essential func-tions during a fire emergency.
4
[
O j~
i
\\
i F
YANKEE-ROWE 6-2 I
.-=
" _.;g.
2=
ADMINISTRATIVE CONTROLS
..z..
6.3 FACILITY STAFF OUALIFICATIONS
=.
I 6.3.1 Each member of the facility staff listed below shall meet or
...._~~ ~
exceed the minimum qualifications of ANSI N18.1-1971 for comparable
^
positions.
=e a.
Plant Superintendent b.
Assistant Plant Superintendne y
c.
Chemistry and' Health Physics Supervisor.
d.
Operations Supervisor u.
Reactor Engiaeer i
f.
Maintenance Supervisor g.
Instrument and Controls Supervisors I
h.
Shift Supervisors u
4 i.
Plant Health Physicist 1
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Coordinator and shall meet or e.v.ceed the requirements and recon:nendations of Sect' ion 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
-6.4.2 A training program for the fire brigade shall be maintained under the direction of a member of the plant staff appointed to perform the duties of Fire Protaction Coordinator and shall meet or exceed the requirements of Section.27 of the NFPA Code-1976.
i 6.5 REVIEW AND AUDIT
/
i l
6.5.1 PLANT OPERATION REVIEW COMMITTEE I
FUNCTION 6.5.1.1 The Plant Operation Review Comittee (PORC) shall function to advise the Plant Superintendent on all matters related to nuclear safety.
==
4 YANKEE-ROWE 6-6.
i
+.... -
- . }~::
, ' L:.
j q-
~
~~
ADMINISTRATIVE CONTROLS 9.:.:
COMPOSITION hh#
6.5.1.2 The Plant Operation Review Comittee shall be composed of the:
gg Chairman:
Plant Superintendent L
Vice Chaiman: Assistant Plant Superintendent Member:
Operations Supervisor Member:
Maintenance Supervisor Member:
Reactor Engineer Member:
Chemistry and Health Physics Supervisor Member:
Instrument and Control Supervisor Member:-
Plant Health Physicist ta::. ~::.
ALTERNATES
- 6.5.1.3 All alternate members shall be appointed in writing by the PORC i
3 Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities or
?i count tosard a PORC quorum at any one time.
1 MEETING FRE0VENCY 6.5.1.4 The PORC shall meet at least once per calendar month an'd hs
. convened by the PORC Chaiman or Vice Chairman.
QUORUM 6.5.1.5 A quorum of the PORC shall consist of a minimum of five people i
as follows:
The Chairman or Vice Chaiman plus' four members, or a.
p:.
b.
The Chairman and Vice Cha'irman plus three members. ---
. RESPbHSIBILITIES -
i 6.5.1.6 The Plant Operation Review Committee shall be responsible for:
Review of 1) all procedures required by Specification 6.8 a.
and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Plant Superintendent to affect nuclear safety.
i l
YANKEE-ROWE 6-7 6
f
.w.
.m.e, am.
em=*
..'.'i
~'
n-. -, - -,-.--
-e-r s
- ~,,-.
a
I s
W:.
NT l~.".
ADMINISTRATIVE CONTROLS b.
Review of all proposed tests and experiments that affect
~
~
nuclear safety.
c.
Review of all proposed changes to the Technical Specifications.
.m i d.
Review of all proposed changes or modifications to plant Q
systems or equipment that affect nuclear safety.
f Investigation of all violations of the Technical Specifications e.
including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager of Operations and to the Chairman of the Nuclear Safety Audit and Review Committee.
f.
Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
g.
Review of facility operations to detect potential nuclear safety hazards.
h.
Performance of special reviews, investigations of analyses and
.H reports thereon as requested by the Chairman of the Nuclear Safety Audit and Review Committee.
- _2..
i.
Review of the Plant Security Plan and ' implementing procedures and shal1 submit recommended changes to the Security Advisor.
j.
Review of the Emergency Plan and implementing proceduras and shall submii recommended changes to the Radiation Protection Manager.
AUTHORITY
- 6. 5.1. 7 The Plant Operation Review Committee shall:
~
l:
Reconnend' to the Plant Su erintendent, written approva1. or dis-a.
approval of items considered under 6.5.1.6(a) through (d) above.
r b.
' Render determinations in writing with regard to'whether or hot each item considered under 6.5.1.6(a) through (e) above 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 of Operations of disagreement between the PORC and the Plant Superintendent; however, the Plant Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
=.z YANKEE-ROWE 6-8 i
- 1
[_ ~
~
?.....
ADMINISTRATIVE CONTROLS RECORDS 6.5.1.8 The Plant Operation Review Committee shall $aintain written minutes of each meeting and copies shall be providad to the Manager of Operations and Chairman of the Nuclear Safety Audit and Review Committee.
g 6.5.2 NUCLEAR SAFETY AUDIT AND REVIEW COMMITTEE FUNCTION 6.5.2.1 The Nuclear Safety Audit and Review (NSAR) Committee shall function to provide independert review and audit of all aspects of plant safety. Adequacy of this review and audit is assured by the cross sec-a=
tion of disciplines required of the Committee membership as described in Section 6.5.2.3.
COMP 0SITION 6.5.2.2 The NSAR Committee shall be composed of at least six persons with the Committee membership and its Chairman and Vice Chairman appointed.
e by the Yankee Atomic Electric Company Vice President or such person as he shall designate.
Ei a.
Cnai rman b.
Vice Chairman c.
Four technically qualified. persons who are not members of the plant staff.
~
OVALIFICATION 6.5.2.3 Membership to the NSAR Committee, requires that an individual meet one of the below academic and/or experience requirements:
Bachelor Degred or 'e'uivaf.ent, plus five (5) years total q
a.
==
experience in the below listed disciplines.
/
b.
Nine (9) years total experience in the below listed. disciplines:
(a) Nuclear Power Plant Technology (b) Reactor Operations -
(c) Utility Operations (d)
Power Plant Design (e) Reactor Engineering (f) Radiation Safety YANKEE-ROWE 6-9 W
u a
=r s
)
ADMINISTRATIVE CONTROLS m
6..n.
REVIEW j
6.5.2.8 The NSAR Comittee shall review:
mys a.
The safety evaluations for 1) changes to equipment or
=
systems and 2) tests or experiments completed under the pro-visions of Section 50.59. 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
i b.
Proposed changes to equipment or systems which involve an unreviewed safety question as defined in Section 50.59,10 CFR.
j c.
Proposed test or experiments which involve an unreviewed i
safety question as defined in Section 50.59, 10 CFR. 1
~
d.
Proposed changes to Technical Specifications or this Operating License.
e.
Violations of codes, regulations, orders, Technical Specifica-i tions, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnomalities or deviations from nomal and expected perfomance of plant equipment that affect nuclear safety, defined as Plant Infometion Reports.
g.
Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Comission.
h.
Reports and meetings minutes of the Plant Operation Review Comittee.
i.
Perfom special reviews and investigations and render reports theren as requested by the Assistant Vice President of 1
Operations.
AUDITS _
6.5.2.9 Audits of facility activities shall be performed under the i
cognizance of the NSAR Comittee. These audits shall encompass:
- a. ~ The confomance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months, + 25%
YANKEE-ROWE 6-11 i
_ ~... -
i
=-=.....-a l
J ADMENiSTRATIVE CONTROLS
=.
b.
The perfomance, training and qualification of those members of the facility staff who have a direct relationship to oper'ation, maintenance or technical aspects of the plant, at least once per 12 months, i 25%.
C..
The results of actions taken to correct deficiencies occur-
~~"
c.
ring in facility equipnient, structures, systems or method of operation that affect nuclear safety at Itast once per 6
=.
months, + 25%.
d.
The perfomance f activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",
10 CFR 50, at least once per 24 months,125%.
The Facility Emergency Plan and implementing procedures at e.
least once per 24 months, i 25%.
f.
The Facility Security Plan and implementing procedures at least once per 24 months, 1 25%.
=
The Facility Fire Protection Program and implement'ng proce-g.
dures at least once per 24 months, i 25%.
h.
Any other area of facility operation considered appropriate by the NSAR Committee or the Vice President.
AUTHORITY 6.5.2.10 The NSAR Committee shall report to and advise the Vice President on those areas of responsibility specified in Sections 6.5.2.8 and 6.5.2.9.
RECORDS 6.5.2.11 Minutes of each NSAR Committee meeting shall be prepared and fomarded to the Vice President and each member of the Committee for review within 20 working days following each meeting. The meeting minutes shall include, where applicable, reports of reff ews encompassed by Section 6.5.2.8; and reports of audits encompassea by Section 6.5.2.9 The review of the minutes shal,1 be completed within 60 days of the date of their distribution.
i6.5.3 INDEPENDENT AUDIT AND REVIEW 6.5.3.1 An independent fire protection and loss prevention program inspection and audit shall be perfomed at least once per 12 months
- utilizing either qualified offsite licensee personnel or an ensite fire protection fir.m 6.'5. 3. 2 An inspection and audit of the fire protection and loss pre-vention program shall be perfomed by a qualified outside fire consultant at laast once per 36 months.
YANKEE-R0WE 6-12 2:.
- L:
L.-.~-...
=
I
)
(
\\
ADMINISTRATIVE CONTROLS 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REP 0kTABLE OCCURRENCES:
a.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
b.
Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PORC and sub-mitted to the NSAR Committee and the Manager of Operations.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The facility shall be placed in at least HOT STANDBY within g
one hour.
~
b.
The Safety Limit violation shall be reported to the Commission, the Manager of Operations and to the NSAR Committee within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
~
c.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the Plant Operation Review Committee. This report shall describe (1) applicable cir-cumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
'd.
The Safety Limit Violatien Report shall be, submitted to the Commission, the NSAR Committee and the Manager of brerations within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained -that meet or exceed the requirem._ats and recommendations of Sections 5.1 and ~5.3 of ANSI N18.7-1972 and-Appendix "A'! of Regulatory Guide 1.33, November 1972, except as provided in 6.8.2 and 6.8.3 below.
The written procedures shall also cover the activities relating to the Fire Protection Program implementation.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the Plant Operations Review Committee and approved by the Plant Superintendent prior to implementa-tion and reviewed periodically as set forth in administrative procedures.
YANKEE-ROWE 6-13
ADMINISTRATIVE CONTROLS 6.8.3 Procedures that have been developed as a result of changes defined in 10 CFR 50.59(a)(2) shall be independently reviewed to verify that the ~
implementing actions do not constitute an unreviewed safety question.
=
Those reviews shall be performed by Nuclear Service Division personnel having qualifications at least equivalent to those specified for NSAR Committee membership in 6.5.2.3.
The procedures shall be approved by the Manager of Operations, NSD.
F 6.8.4 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at -least one of whom holds a Senior Reactor Operator's License.
c.
The change is documented, reviewed by the PORC and approved by the Plant Superintendent within 14 days of implementation.
6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Reg'ional Office of Inspec-tion and Enforcement unless otherwise noted. The reporting requirements of Specifications 6.9.1, 6.9.2, 6.9.3 and 6.9.4 are in accordance wi'5 Revision 4 of Regulatory Guide 1.16, " Reporting of Operating Informe;_on -
Appendix "A" TechnicaT Specifications."
ROUTINE rep 0RTS 6. 9.1 Startuo Reoort. A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendme,nt to, the license involving ~and planned increase in power level, (3) installation of fuel that has a different fuel supplier, and (4) modifications that may have significantly' altered
.the nuclear, thermal, or hydraulic perfor.mance of the plant. The riport shall address each of the tests identified in the FHSR and shall in general include a description of measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be
- 1 included in this report.
j
~!
YANKEE-ROWE 6-14 j
I ADMINISTRATIVE CONTROLS Startup reports shall be submitted within (1) 90 days. following com-pletion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If.the Startup Report does not cover all three events (i.e., initial criticality, completion of is startup test program, and resumption or commencement of commercial power b
operation), supplementary reports shall be submitted at least every f:
three months until all three events have been completed.
~
6.9.2 Annual Operating Report.
Routine operating reports covering the operation of the unit during the previous calendar year shall be sub-mitted prior to March 1 of each year.
The initial report shall be submitted prior to March 1 of the year following initial criticality.
The annual operating reports made'by licensees shall provice a compre-hensive summary of the operating experience gained during the year, even though some repetition of previously reported information may be involved. References in the annual operating report to previously sub-mitted reports shall be clear.
Each annual operating report shall include:
a.
A narrative summary of operating experience during the report period relating to safe operation of the facility,
~
including safety-related maintenance not covered in item b(5) below, b.
For each outage ~ or forced reduction in power
- of over twenty percent of design power level where the reduction extends for greater than four hours:
(1) The proximate cause and the system and major component involved (if the outage or' forced reduction in power involved equipment malfunction);
(2) A brief discuss' ion of (or reference to reports of) any REPORTABLE OCCURRENCES pertaining to the outage or' power reduction; (3) Corrective action taken to reduce the probability of recurrence, if appropriate;
" Forced reduction in power" is defined as the occurrence of a component failure or other condition which requires that the load on the unit be reduced for corrective action immediately or up to and including the very next weekend.
Routine preventive mainten-ance, surveillance and calibration activities requiring power reductions are not covered by this section.
l YANKEE-ROWE 6-15 l
j l
~
ADMINISTRATIVE CONTROLS (4) Operating time lost as a result of the outage or power reduction (for scheduled or forced outages,** use the generator off-line hours; for forced reductions in power, use the approximate duration of operation at '
reduced power);
.=7 (5) A description of major safety-related corrective main-tenance performed during the outage or power reduction, including the system and component involved and identi-fication of the critical path activity dictating the length of the outage or power reduction; and
=
(6) A report of any single release of radioactivity or radiation exposure specifically associated with the outage which accounts for more than 10% of the allowable annual values.
c.
A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions,*** e.g.,
reactor operations and surveillance, inservice inspection, si routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted fo r.
In Ute aggregate, at least 80% of the whole body dose received fre.n external sources shall be assigned to specific major work functions.
i d.
Indications of failed fuel resulting from irradiated fuel examinations, including eddy current tests, ultrasonic tests, d
or visual examinations completed during the report period.
6.9.3 Monthly Operatino RepetE.
Routine reports of operating statistics.
and shutdown experience st:ll be sub'mitted on a monthly basis to.the Office of Inspect' ion and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. '20555, with a copy to the appropriate Pegional Office, to arrive no later than the tenth of each month following the calendar month covered by the renort.
" Forced outage" is defined as the occurrence of a component failure or other condition which requires that the unit be removed from service for corrective action immediately or up to and including the very next weekend.
This tabulation supplements the requirements of 5 20.407 of 10 CFR Part 20.
YANKEE-ROWE 6-16
?
'i' ADMINISTRATIVE CONTROLS REPORTABLE OCCURRENCES 6.9.4 REPORTABLE OCCURRENCES, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC.
Supplemental, reports may be required to fully describe final resolution of occurrence.
In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
a.
Prompt Notification With Written Followup.
The types of events listed below shall be reported as expeditiously as possible, but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the appropriate Regional Office, or his designate no later than the first working day following the event, with a written followup report within two weeks.
The written followup report shall incl ~ude, as a minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide a complete explanation of the circumstances surrounding the event.
(1) Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the Technical Specifications or failure to complete the required protective function.
Note:
Instru;ent drift discovered as a result of testing need not be reported under this item but may be reportable under items a(5), a(6), or b(1) below.
(2) Operation of the unit or af fected systems when any param-eter or operation subject to a limiting condition is less conservative than the least conservative as.pect of the limiting condition for operation established in the Technical Specifications.
Note:
If.specified action is taken when a system is,found to be oper~at'ing between'the most conservative ~ and the least -
conservative aspects of a limiting condition for opera-tion listed in the Technical Specifications, the limiting condition for operation is not considered to have been violated and need not be reported under this item, but it may be reportable under item b(2) below.
(3) Abnormal degration discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
YA"KEE-ROWE 6-17
i t,
l l
.... l ADMittISTRATIVE C0!1TROLS Note: Leakage of valve packing or gaskets within.the limits for IDENTIFIED LEAKAGE set forth in Technical Speci-fications need not be reported under this item.
.I (4) Reactivity anomalies, involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation, greater than or equal to 1% ak/k; a calculated reactivity balance indicating a shutdown margin less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds.
or, if sub-critical, an unplanned reactivity insertion of more than 0.5% ak/k; or occurrence of any unplanned criticality.
- 9.
.' ( 5 ). Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the FHSR.
(6) Personnel error or p'rocedural inadequacy which prevents or could pr. event, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the FHSR.
Note:
For items a(5) and a(6), reduced redundancy that does not result in a loss of system function need not be reported under this section but may be report 3ble under items b(2) and b(3) below.
(7) Conditions arising from natural or man-made events that, as a direct result of the event require plant shutdown, operation of safety systems, or other' protective measures required by technical specifications.
(8) Errors discovered in the trans'ient or accident analyses or in the metho'ds used for such analyses as described i
in the FHSR or in the Bases for the Technical Specifications that have or could have permitted reactor operation in a ma'nner l'ess conservative than-assumed in the analyses.
(9) Performance of structures, systems, or components that requires remedial action or corrective measures to pre-vent operation in a manner less conservative than assumed in the accident analyses in the FHSR or Technical Specifica-tions Bases; or discovery during plant life of conditions not specifically considered in the FHSR or Technical Specifications that require remedial act' ion or corrective measures to prevent the existence or derf opment of unsafe conditions.
YANKEE-ROWE 6-18 O
=
ADMINISTRATIVE CONTROLS Note: This item is intended to provide for reporting of potentially generic problems, c
m.
b.
Thirty Day Written Reports.
The REPORTABLE OCCURRENCES di's-
...g cussed below shall be the subject of written. reports to the Director of the appropirate Regional Office within thirty days of occurrence of the event.
The written repcrt shall include, b
as a minimum, a completed copy of a licensee event report E
form.
Information provided on the licensee event report form shall be supplemented, as needed, by assitional narrative material to provide : implete explanation of the circumstances surrounding the event.
(1) Reactor protection system or engineered safety feature instrument settings which are found to be less conser-vative than those established by the Technical Specifi-
+.
cations but which do not prevent the fulfillment of the
%=:
functional requirements of affected systems.
(2) Conditions leading to operation in a degraded mode per-mitted by a. limiting condition for operation or plant shutdown. required by a limiting condition for operation.
Note: Routine surveillance testing, instrument calibration, or preventative maintenance which require system configurations as described in items b(1) and b(2) need not be reported except where test results them-selves reveal a degraded mode as described above.
(3) Observed inadequacies in the implementation of admin-i istrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
(4) Abnormal degradation.of systems other than those specified in item a(3) above designed to. contain radioactive material
~
resulting from the fission process.
~
~ '
Note: Sehled ' sources or' calibration ~ sources are* not ' included under this item.
Leakage of valve packing or gaskets within the limits for IDENTIFIED LEAKAGE set forth in Technical Specifications need not b'e reported under this item.
m 6.9.5 Unique Reporting Requirements g
a.
Environmental Radiological Monitoring f
H H
YANKEE-ROWE 6-19
-1 y
-.m.>
_.,_y r-m
b
,m a
.1:
.y '
ADMIfilSTRATIVE C0f4TROLS r
(d) Total dissolved gas radioactivity (in curies) and 1.. """
average concentration released to the unrestricted area.
1 (e) Total volume (in liters) of liquid waste released.
(f) Total volume (in liters) of dilution water used prior i
to release from the restricted area.
(g) Total gross radioactivity (in curies) by nuclide released based on representative isotopic analyses i
performed.
(h) Percent of Technical Specification limit for total radioactivity.
l (3) Solid Wastes (a) The total amount of solid waste shipped (in cubic feet).
I (b) The total estimated radioactivity (in curies) involved.
i (c) Disposition including date and destination.
6.9.6 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period
)
specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the I
applicable reference specification:
I a.
Inservice Inspection Program Reviews, Specification 4.4.9.1.
b.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
c.
Inoperable Meteorological Monitoring Instrumentation, Specifi-cation 3.3.3.3.
i Sealed Source leakage in excess of limits, Specification 4.7.6.3.
e.
Radioactiv~e Solid Waste Disposal, Specification 3.7.9.1.
g.
Fire Detection Instrumentation, Specification 3.3.3.4 1.
Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2 i
and 3.7.11.3.
YAf4KEE-ROWE 6-22 3
-~ ~
~
~~
' 72 :
. - ~ -
4 a
--=aa
,.n_.-
e x._.-
.s-_.-
a s-.
4 0
I
,9*
.3 5 3 a **
VR2
=33 g
w=
5 t *gut u
u 3JA 4
8 u=
30g:2 g
3c!!
3-3 12 i s-al a
Jh 33
=g g 5
1<
p
,, p.
g
==
4g s.
su Io 8
3 4&
a303 33 u,
EE8 g3 14 C
b 2
2 wa uL4
=
44 j l3 bl
- E e
G "3
- J
!n
- ::r ag gbb e.
$5 4
i j
' ?
2 4
R33 ta"
<s ne YAXEE R&R E
O 6-3
.=
1 Eurcriarindant
[
j k
pj Assistaat l*
N
~
Plant m
e 5eparinradaar f
~. - -
I n
i l
Instrussot &
OTachaical Chemistry 4 i
Administrative Maintsaasca Operations Saaster Castrais Assistaat tosha, Maalth Physica.
j Superviser supervisar supervisors superviser h
P1m Sgt.
Sgarvisar I
E e
i Assistaat Operations
[
superviser t
Adataistrative Madmea=anea shift Emaccar h t m aatstian Tschaical il'"C m;
}
Organisation Organisettaa Supervisor tagianering
& Controis 4,,g,g,,g haith b
Assistanta Organisatica Physictat c
<g.g}
rm (f3 )
&;w w
Err * ')
(ski
/
-r,
)
Control Room Chamistry 6 APS N**"'8 h$h j Organizatica Haalth Phy=iu QrinniutLca [Cr a h ^ i 1-u ia,y @4rs co ra pggo,,e 6.2-2 We F1#E pao 1ECT)ou T> fogy ~ gig MPQAJSIBlU TY 'W:3 FACILITY ORGMI2ATI0ff t Ks masa
- d '
,}}