ML19209C225
| ML19209C225 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/21/1979 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML19209C224 | List: |
| References | |
| NUDOCS 7910120222 | |
| Download: ML19209C225 (23) | |
Text
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TABLE 15.3.13-1 -
~
SAFETY RELATED SECCK SUPPRESSORS (SNUEBERS)
Snubber in Snubber Snubber Snubber High Radiation Especially Inaccessible Accessible Locatien Arca During Difficult to During Normal During Normal' D Nanber Location Elevation Shutdown
- Recove Operation Cperation Unit 1 l l-HS-1 "A" Main Steam Line - West 100 X
!l-ES-2 "A" Main Stean Li*ne - East 100 X 1-HS-5 "A" SG Side - North 66 X (2) 1-HS-6 "A" SG Side - Middle 66 X (2) i 1-MS-7 "A" SG Side - South 66 X (2)
I
- l-HS-3 "B" Main Stean Line - West 100 X
' l-::3-4 "B" Main Stear. Line - East 100 X l-H5-3 "E" SG Side - North 66 X (2)
"4 C3 ll-HS-9 "B" SJ Side - Middle 66 X (2) w l l-H3-10 B" SG Side - Scuth 66 X (2)
CD 1-E3 l' "n" Mair reed Line at 66' 61 X
- l-rs-15 Containrent spray Header Above 66' 120 X IE 1-US-16 Contain::cnt Spray Header Above 66' 120 X CD '
l-HS-17 Pressuriner Relief Line 80 X SJ ll-3S-18 Pressuriner Relief Line 80 X SJ !l-HS-14 Pcwer Operated JIeader-Pressuriner 78 X 33 , Cubicle
' l-ES-::74 Folief Valve Headcr-Pressurizer 80 X Cubicle
, 1-HS-12 SIS Line - Regen. HX Cubicle 34 X X (2)
!i l-ES-13 SIS Line at 21' Elevation 40 X
-* ! 1-HS-19 l Reactor Vessel Xeyway 3 X (1) X j 1-25-23 Recctor Vessel Kcyway 3 X (1) X 2s b - gni e &
n l2-HS-36 "A" SG Side - north 66 X (2)
L/4 i 2-ES-27 "A" SG Side - Middle 66 X (2)
C7s ' I 2-H3-2 8 "A" SG Side - South 66 x (2) 2-H3-32 'A" !:ain Stear Line - East 100 X I 2-ES-33 } "A" .:ain Stear Line - West 100 X 2-US-39 "B" SG Side - North 66 X (2) 1 2-FS-40 "B" SG Side - Middle 66 X (2)
ES-41 "B" SG Side - South 66 X (2)
___. , f, 9
TABLE 15.3.13-1 (Continued)
Snubber in Snubber Snubber Snubber High Radiation Especially Inaccessible Accessible Snubber Area During Difficult to During Normal During Normal ID Uurter Location Elevation Shutdown
- Eemove Operation . Operation 2-HS-34 "B" Main Stean Line - East 100 f X 2 -i:S-3 5 "B" '*ain Stean Line - West 1CO ,
X 2-HS-21 Aux. Feed Line to "A" SG 72 X 2-US-23 SIS Line (.t 46' 50 X 2-ES-26 l SIS Line at 46' 34 ! X
'2-PS-24 At Overhead to Keyway at 26' 36 h X 2-HS-29 Cownctrean of Valve PCV 434 80 X 2-FS-30 Cownstrear of Valve PCV 435 80 X 2-i:S-M7 5 Downctream of Pressurizer Safety 80 X Valve 2-HS-28 Line to Power Operated Relief 77 X valves 2-HS-22 Eeneath Valve 541 in "A" Loop 41 X X Cubicle 2-ES-31 Reactor Vessel Kefway 3 X (1) X 2-HS-27 Reactor vessel Keyway 3 X (1) X 2-1:5-25 Regen. HX Cubicle at 26' 34 X X (2)
(1) High radiation during shutdown eith flux thimble withdrawn.
~~'*
(2) Accessible during normal operat on for visutl inspection or ly.
. .h 4
- 1:cdifications to this Table due to changes in high radiation areas shall
_. be submitted to the NRC as part o the next IJ censo amendment .
U
'sa ,
TAB L , 15 . 4 .1-1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Description Check Calibrate Test Remarks
- 1. Nuclear Power Range S (l) *
- D (1)** D/W (2)** 1) Heat balance M*(3)** Q*(3)** 2) Signal to AT; bistable action (permissive, rod stop, trips)
- 3) Upper and lower chambers for axial off-set
- 2. Nuclear Intermediate Range S (l) *
- N.A. P (2) 1) Once/ shift when in service
- 2) Log level; bistable action (pernissive, rod step, trips)
- 3. ';uclear Source Range S (1) N.A. P (2) 1) Once/ shift when in service
- 2) Bistable action (alarm, trips)
Reacter Coolant Terperature S . R B/W (1) *
- 1) Cvertemperature-Delta T 4.
(2) 2) Overpower - Delta T
- 5. Reactor Coolant Flow S** R M**
- 6. Pressurizer Water Level S** R M**
- 7. Pressuriner Pressure S** R M**
~ I'v Voltage & Frequency N.A. R M** Reactor protection circuits only 8.
- 9. Analog Rod Position S (1)** R M** 1) With step counters
- By means of the novable in-core detector system.
- Uct required during periods of refueling shutdown, but must be perforecd prior to starting up if it has not been perforred during the previous surveillance period. Tests of permissive and low power trip bistable setpoints which carnot bc done during power operations shall be conducted prior to startup if not done in the previous two weeks.
I!44 138 .
15.5 DESIGN PimTURES 15.5.1 SITE Applicability Applies to the location and extent of the reactor site.
Objective To define those aspects of the site which affect the overall safety of the installation.
_ Specification The Point 1:,cach Nuclear Power Plant is located on property owned by Wisconsin Electric Power Company at a site on the shore of Lake Michigan, approximately 30 niles southeast of the city of Green Day. The miniuum distance from the reactor containraent center line to the site exclusion boundary as defined in 10 CFR 100.3 is 1200 meters.
15.5.1-1 ) 4 139
15.6 AICINISTFATIVE CONTROLS 15.6.1 RESPONSIBILITY 15.6.1.1 The Manager - Nuclear Operations shall be responsible for overall facility operation and shall delegato in writing the succession to this responsibility during absences from the Point Ecach Nuclear Plant area of greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and where ready contact by telephone or other meann is not assured.
15.6.2 ORGANIZATION JPFSITE 15.6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 15.6.2-1.
FACILITY STAFF 15.6.2.2 The Facility organization shall be as shown on Figure 15.6.2-2 and:
- a. Each on-duty shift shall normally be composed of at least the mininum shift crew composition as noted in Figure 15.6.2-2.
- b. At least one licensed Operator shall be in the control room when fuel is in either reactor.
- c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
- d. An individual qualified in radiation protection procedures shall be on site when fuel is in either reactor.
- c. ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Ennior Peactor Operator or Senior Ipactor Operator Limited to I'uel Handling who has no other concurrent responsibilitieu during this 1 1AA 1An operation. II 4 8 4U 15.6.1/2-1
BOARD OF DIRECTORS PRESIDEitT WISC0NSIri ELECTRIC POWER COMPANY i
GTHER EXECUTIVE VICE PRESIDENT OFF-SITE DEPARTi:ENTS WISC0iiSIN ELECTRIC PCWER C071PAi;Y REVIEW COMMITTEE DIRECTOR I'UCLEAR PCUER DEPARTIENT SUPERINTEi; DENT SUPERIf1TEiiDEriT MANAGER QUALITY fiUCLEAR PROJECTS OFFICE NUCLEAR OPEPATIONS ASSUPAriCE
.s MANAGER'S
_ SUPERVISORY s STAFF MANAGEMENT ORGANIZATION CHART FIGURE 15.6.2-1
c:anager - (1) ______________________ _ - - - --- ________________________
n-u.e.. ceru, lono (NJ .
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Manager's Suocrvisorv l 7.scistant to (1) '
Staff Ccnnittee f the Managcr q I
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i I
i 1
OPERATIONS TRAINING MAINTETANCE & TECHNICAL SERVICES i t I CONSTPUCTION :
i t
i Supcrintendent (1) Superintendent (1) ,a Superintendant - (1) Training (l)
Maintenance & Tcchnical Services C h. _u . .q o _ ,i n., &
.l, CPerations (FRO) Supervisor Construction InSThuMEni I HEALTH PiiYSICS 8 i
& CONTROL REACTOR ENGINEERING
' i l Technical (1) Instrument & Reactor Radic che.r.ical ,I n,o c, m . s t a..t Control Eng. (1) Engineer (1) Engine 2r (1) i s
t I !
l Shift Supervisor (SRO) Maintenance NUd5EU II) --
Technical Physicist l Cne ner shif t Sunervisors Assistants 1
Tcchnicians Operating Supervisor Technical Onc par shif t(SRO or RO Assistants Notes:
- 1. The Operations Group chift makeup is the minimum' size for operation in all
--- 3, C e "--*--
- - ( "- ^s '> = cats except cold shutdown of Point Beach Unit Nos. 1 and 2. The Cper-vs . .e, , , _
zu. .,.4
. . . _v..e un;t ations Group shift makeup nay be less than the nininun rcquircrents for a Two pcr shift-two units 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 of on-duty shift crew members, provided immediate action is taken l to restore the shif t takeup to within the mini:..am requirements.
Auz..iicry Opcrator 2. Health Physicist has optional reporting route to Manager on radiological Two per shift-cne unit health and safety matters.
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." u"'4*s" SRO - URC Senior Reactor Operator License 3.
RO - URC Reactor Operator License CCNDUCT OF PL7Cir OPERICIONS CHART Figure 15.6.2-2
en w
President e w
g i I I
Treasurer Executive Vice President l
Superintendent System Security & Fire Prote . ton Superintendent of Insurance and Claims (NEL-PIA and !i."L)
Director - f,'aclear System Fire Protection Officer Pcwer Department I
Fire Insurance Superintendant Consultants, {
Designers & I t;uclear Prc]ects Or, rice Inspectors ftanager -
I;uclear Oparations Point Beach Nuclear Plant Fire Protecticn
- Design Consultant WISCO.71SIfl ELECTRIC PCWER C0".PA:1Y OFF-SITE ?MilAGEl:E!1T FIRE PROTECTIO!4 ORGAt1IZATICri - - - Administrative Organization FIGURE 15.6.2-3 Fire Protection Organizaticr.
<r er
<:r c-f'.anager - ~
i;uclear Operations, PariP f 8 1 i Security Superintendent - Superintendant -
Su'ervisor Maintenance Operations I I
l l l l } l I
I Fire Protection Supervisor Training Supervisor i I 1
i I l l
Fire Brigade Chiefs (5) l (Operations Supervisors - 1 I
l cer shift)
{ i I i
! Asst. Fire Brigade Chiefs (2) Asst. Fire Brigade Chiefs (5} Two Creeks '!cluntear General Foreman-l'.aintenance (Operationssupervisors-1l, Fire Departrent
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Contrac*' Maintenance Brigade Operations Brigades - - - Adm.inistrativc Cg S& y Organizaticn (10 Iiembers) (25 mecbers total)
Fire Protection Organizaticn POIliT BEACH ::UCLEAR PLA!!T FIRE PROTECTIO:1 ORGAtlIZATIO:1 FIGURE 15.6.2-4
15.6.3 PACILITY STAPI' OUALIFICATIO!!S 15.6.2.1 I:ach member of the facility craff shall meet or exceed the ninimum qualifications of AIISI tt18.1-1971 for comparable positions.
15.6.4 TPaTts M_G 15.6.4.1 A retraining and replacement training progran for the facility staff chall be maintained under the direction of the Training Supervisor and shall neet or exceed the require:r.ents and recotr.cndations of Section 5.C c f AE
!!18.1-1971 and Appendix "A" of 10 CFR Part 55.
15.6.4.2 A training prograu for the rire Drigade chall be maintained under the direction of thc. Fire Protection Supervisor and shall meet or exceed the requirenents of Section 27 of the I:ITA Code-1976, except that the meeting frcquency nay be quarterly.
15.6.5 11EVIEW AND AUDTT 15.6.5.1 Duty and call Superintendents
- a. "Jo assist and councol the Shift Supervisor in case of cignificant operating events, a Duty and Call Superinter. dent Group has been established. The Duty and Cull Superintendent Group shall consist of any qualified pornon designated by the Manager - I!uclear Operations,
- b. In the event of a reportable occurrence, the Shift Supervisor shall coumunicate with at least one Duty and Call superintendent Lefore taking other than the imnediate on-the-spot action iequired.
One , Duty and Call Superintendent will be assigned to be "on c.'ll" at all times. The Duty and call Superintendent provides contii..ously availab]c counnel, call out backups, and review to the Shift Supervicor.
15.6.5.2 Manager'r. Supervicory Staff PUI;CTION
]5.6.5.2.1 The Manager's Supervisory Staff (112 S ) shall funct'on to advise the.
i flaaager - Muclear Operationu on all Mattern related to nuclear cafety.
ye 15.6.3/4/5-1 -}1 'k )N)
CC:tPOSITIO!1 15.6.5.2.2 The !!anager's Supervisory Staff chall be composed of the:
Chairman: Manager - fluclear Operation..
Member: Superintendent - Operations flembe r : Superintendent - Maintenance & Construction l'embe r : Instrument and Control 1:ngineer
!! ember : Superintendent - Technical servicen fember: Radiochemical 1:ngineer tiercher : IIcalth Physicist
!1 ember: Assistant to the Manager - L'uclear Operations AI!rEIU:ATES 15.6.5.2.3 Alternate merters chall be appointed in writing by the MSS Chairman to serve on a temporary basis; however, no more than two alternaten shall participate in !!SS activities at any one time.
MEET 1tM FREOUE: CY 15.6.5.2.4 The MSS shall meet at least once per calendar month and as convened by the liSS Chairman.
OUORU1 15.6.5.2.5 A quorum of the USS shall consist of the Chairmen and four mem-born including alternates.
RE9PO"SIBILITIES' 15.6.5.2.6 The IRnager's Supervisory Staff shall:
a) Review existing and proposed normal, abnormal and cmergency operating procedurcs. noview' maintenance procedureu and proposed changes to these procedures and other procedures or changes thereto as determined by the flanager to affect plant operational safety. (nc: Section 15.6.7 for area of review.)
1144 146
, 5 . n . 5 .,
b) Review all proposed tests and experiments related to safer-and the results thereof when applicabic, c) Review all proposed changes to Technical Specifications, d) Review all proposed chan3cs or modifications to plant systems or equi >1 ment where changes would require a change in operating or energency procedures or that affect nuclear safety.
c) Periodically review plant operations for industrial and nuclear safety hazards.
f) Investigate violations or suspected violations of Technical Specifications, such investigations to include reports, evaluations, and recommendations to prevent recurrence, to ' ' .e Executive Vice President and to the Chairman of the off-site Review Corcaittee, g) Perforn special reviews and investigations and prepare reports thereon as requested by the Chairnan of the off-Site Review Committee.
h) Investigate, review, and report on all reportable occurrences.
i) Cause to be conducted periodic drills on emergency procedures, including evacuation (partial or complete) of the site and check adequacy of communications with off-site support groups.
j) Review the racility Fire Protection Program and implementing procedures at least once per 24 months.
AUTl!ORITY 15.6.5.2.7 a) The Supervicory Mtaff shall serve as advisory to the Manager -
Nuclear Operations.
b) The Supervisory Staff. shall reccrerond to the Manager approval or disapproval of pr*cposals under items a) through d) above.
In the event of disagrecuent between a majority of the 15.6.5-3 'e4 1 147
Supervisory Staff and decisions by the Aanager, the course of action will be determined by the !!anager and the dis-agreenent recorded in the Staff minutes. Records of the dicagreement will be included in the ninutes sent for ruview to the Off-Site Review Coi:=ittee and the Executive Vice President.
c) The Supervisory Staff shall make tentative recommendations as to whether or not proposals concidered by the Staff involve tutreviewed safety questionc. These recommendations chall be subject to review and further recommendations by the Off-Site Review Concaittee. Minutes chall be kept of all meetings o'f the Staff and copics cha]1 be sent to the Executive Vice President and to the Chairman of the Off-Site Review Committee.
d) The Supervicory Staff chall review and approve the contents of a report for each reportable occurrence. This report shall include an evaluation of the cauce of the occurrence and recontendations for appropriate action to prevent or reduce the probability of a recurrence. Copies of all such reports shall be subnitted to the Executive Vice President and to the Off-Site Review Corr.ittee.
RECOhDS 15.6.5.2.8 The !! ann.ger's Supervicory Staff shall maintain written minutes of each mcoting and copies shall be provided to the E::ecutive Vice President and Chairman, Off-Site Review Committee.
15.6.5-4 }i0k i
15.6.5.3 OFF-SITE ltLVILW CO:::11TTEC (OSRC)
FU!CTION 15.6.5.3.1 The off-Site Review Committee chall function to provide independent revicw and audit of designated activities in the areas of:
a) nuclear po'.ter plant operations b) nuclear engineering c) chenistry and radiochemistry d) netallurgy e) instrumentation and control f) radiological safety g) nochanical and clectrical engineering h) quality assurance practicca i) environmental rc.onitoring CC" POSITION
'15.6.5.3.2 The Off-Site Review Connittee is made up of a ninimum of five regular nembern appointed by the Executive Vice President and one ex-officio ncmber. Of the five or nore regular ncmberc, at least two will be persons not directly en;Ooyed by the Licensee. All members will be experienced in one or more aspects of the nuclear industry. The ex-officio member will be the Exccutive Vice President.
ALTERNATES 15.6.S.3.3 Alternate penbers may be appointed in writing by the OSRC Chairman to serve on a temporary banis; however, no more than two alternates shall participate in OSRC activities at any one tina.
CO:;SULTANTS 15.6.5.3.4 Concultants shall be utilined as detoimined by the OSRC Chairman to provida expert advice to the OSRC.
11^4 149 15.6.5-5
h) Any indication of an unanticipated deficiency in uomo aspect of design or operation of safety related structures, systems, or components.
i) Reports and meeting minu? m of the Manager's Supervisory Staff.
AUDITS 15.6.5.3.8 Audi.s of facility activitics snall be performed under the cognizance of the OSRC. These audits shall encompass:
a) The conformance of facility operation to provision:
contained within the Teclutical Specifications and appli-cable license conditions at least once per year.
b) The performance, training and qualifications of the licensed operating staff at least once per year.
c) The results of actions taken to correct deficiencies occurring in facility equipment, structurcs, systens or method of operation that affect nuclear safety at least twice per year at approximately six nonth intervals.
d) The results of quarterly audits by the Quality Assurance Division on the performance of activitics required by the Quality Assurance Program to moet the criteria of Appendix "B",
10 CPR 50, at least once per two years.
c) rmergency Plan and implenenting procedures at least once per two years.
f) Any other area of facility operation considered appropriate by the Executive Vice President.
AUTHORITY 15.G.5.3.9 The OSRC chall report to and advice the Fxecutive Vice President on those areas of responsibi.lity sp0cificd in Section 15.6.5.3.7 and 15.6.5.3.8.
i144 150 15.6.5-7
RECOPDS 15.6.5.3.10 Records of OSRC activitics shall be prepared, approved and distributed as indicated below:
a) Minutes of each OSRC meeting shall be prepared, approved and
'orwarded to the Executive Vice Precident within 14 days following each meeting.
b) Reports of reviews encompassed by Section 15.6.5.3.7.e, f and g above, chall be prepared, approved and forwarded to the Executive Vice President within 14 d2ys following com-pletion of the review.
c) Audit reports enconpassed by Section 15.6.5.3.8 above, shall be forwarded to the Executive Vice President and to the management positions responsible for the areas audited within 30 days after cor.pletion of the audit.
15.6.5-3
15.6.6 REPORTAnL1: OCCURRE::CI: ACTIO:1 Specification The following action shall be taken for REPORTABLE OCCURREJCES A. The Cor.:qission shall be notified and/or a report subnitted pursuant to the requirements of Specification 15.6.9.2.
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 Cor.tnission shall be reviewed by the fttnager's Supervisory Staf f (MSS) and submitted to the Of f-Site Review Corraittee (OSEC) and the Executive Vice President.
C k fsz^
15.6.6-1
15.6.7 ACTICII TO DE TAKE11 IF A SAPETY LIMIT IS EXCEEDED Speci fi cation A. If a safety limit is exceeded, the affected reactor shall be shut down and reactor operation shall not be resumed until approval is received from the liRC.
B. An immediate report shall be made to the Executive Vice President and the Chairman of the Off-Site Review Committet.
C. The Executive Vice President shall report the circumstances to the
!!RC.
D. A Safety Limit Violation Report including a complete analysis of the circumstances leading to and resulting from the occurrence, effects upon facility components, systems or structures, together with recommendations to prevent a recurrence, shall be prepared. This report shall be submitted to the Executive Vice President and the Chairman of the Off-Site Review Comnittee. A Safety Limit Violation Report shall be submitted to the liRC by the Executive Vice President within 10 days of the occurrence.
15.6.7-1 ii'4 153
15.6.8 PLA!!T OPr:RATI!!G PROCEDUPIS 15.6.8.1 The plant shall be operated and maintained in accordance with approved procedu. s. Major procedures, supported by appropriate minor procedures (such as checkoff lists, operating instructions, data sheets, alarm responses, chemistry analytical procedures, etc.) shall be provided for the following operatior.s where these operations involve nuclear safety of the plant:
- 1. !!ormal ccquences of startup, operation and shutdown of components, systems and overall plant.
- 2. Refueling.
- 3. Specific and foreseen potential malfunctions of systems or components including abnormal reactivity changes.
- 4. Security Plan Implementation.
- 5. Eraergencies which could involve release of radioactivity.
- 6. Iluclear core testing.
7 Surveillance and Testing of safety related equipment.
- 8. Fire Protection Implementation (to be provided by !! arch 31, 1978).
15.6.8.2 Approval of Procedures A. All major procedures of the categories listed in 15.6.8.1 (except 15.6.8.1.4) and 15.6.11, and modifications to the intent thereof, shall be 1
revicued by the Manager's Supervisory Staff and approved by the Manager -
IJuclear Operations prior to implementation.
B. flinor procedures (checkoff lists, operating instructions, data sheets, alarm responses, chenistry analytical procedures, technical instructions, special and routine maintenance procedures, laboratory manuals, etc.) shall, prior to initial use, be reviewed by the !!anager's Supervisory Staff and approved by the !!anager - Nuclear Operations.
11e4 154 15.6.8-1
15.6.0.3 Changes to Procedures A. Tenporary changes to major procedures, of the categories listed in 15.6.8.1 (except 15.6.0.1.4) and 15.6.11.1, which do not change the intent of the original or subsequent approved procedure, may be made provided such changes to operating procedures are approved by the Duty Shift Supervicor and one of the Duty and Call Superintendents. For temporary changes to major proceduren under the jurisdiction of Maintenance, Instrumentation and Control, Reactor Engincering, or Chemictry and Health Physics which do not change the intent, changcu nay be made upon approval of the cognizant group head and a Duty and Call Superintendent. All Temporary changen to najor procedures (made by a Duty and Call Superintendent and either a cognizant group head or the Duty Shift Supervisor) shall subsequently be reviewed by the Manager's Supervisory Staff and approved by the Manager - I;uclear Operations within 2 wechs; except that terporary changco to major procedure made to a given unit during its refueling outage may be reviewed and approved at any time prior to initial criticality of the reload core; and shall only become permanent changen after the !!anager's Supervisory Staff'c review and IIanager's approval ctops.
B. All ter.porary or permanent chengcc to minor cierating procedurcs (checkoff lists, alarm responces, data chects, operating instruc-tions, etc.) shall be approved by the Duty Shift Supervisor, and shall be subsequently revie'.ted and app?oved by the Superintendent - Operation.n. All temporary or pernanent enanges 15.6.8-2
to other rainor procedures under tha jurisdiction of Maintenance, Instrumentation and Control, Ecactor Engineering, or Chemistry and IIcalth Phycies, shall be approved by a supervisor of the cognizant group and shall be subsequently reviewed and approved by the group head of the cognizant group.
u..c.c-3 1i44 156
15.6.9 PIRIT RI: POP.TI!:G RF{UI]E!!TS In addition to the applicable reporting requirements of Title 10, Code of Pederal Regulations, the following program for reporting of operating information shall be followed. Reports should be addressed to the Director, Office of Inspection and Enforcement, Region III unless othorwise noted.
15.6.9.1 Routine Reports A. Startup Report
- 1. A summary report of plant startup and power escalation testing which addresses each of the tests identified in the FFDSAR and includes a general description of the measured values obtained during the test program and a comparicon of these values with design predictions and specifications must be submitted under the following conditions:
- a. Peceipt of an operating license.
- b. Amenar.ent to the license involving a planned increase in power level.
- c. Installation of fuel that has a different design or has been manufactured by a different fuel supplier.
- d. Modifications that may have significantly
' altered the nuclear, thernal, or hydraulic performance of the plant.
Any corrective actions that were required to obtain naticiactory operations shall also be described.
- 2. 7 hic beport chall be suluitted within the earlicut time f rarie of the following:
15.6.9-1 11'4 157
- 9. Performance of structures, systems, or components that requires remedial action or corrective reasures to prevent operation in a manner less conservative than that assumed in the accident analyses in the safety analysis report or techn t. cal specifica-tions bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
B. Thirty-Day Written Reports The types of events listed in items 1 through 4 below have lesser immediate importance. These events shall be the subject of written reports to the Director, Office of Inspection and Enforcement, Ecgion III within 30 days of the occurrence of the event. The written report shall include, as a minimum, a completed copy of the licensee event report form, and may be supplemented, as needed to provide complete explanation of the circumstances currounding the event, l.
Reactor protection systen or engineered safety feature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.
- 2. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
15.6.9-G