ML19317G894
| ML19317G894 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/16/1977 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19317G892 | List: |
| References | |
| NUDOCS 8004020552 | |
| Download: ML19317G894 (17) | |
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RANCHO SECO UN!7 i TECHNICAL SPECIFILATIONS DEFINITIONS 1.9.4 Monthly - A time period from the first to last day of a calendar month spaced to occur 12 times a year.
1.S.5 Quarterly - A time period of three calendar months spaced to occur 4 times a year.
1.9.6 Semi-Annual - A time period from January I and July I covering the subsequent six months.
l.9.7 Blannually - A time period of 24 calendar months spaced to occur once in two years.
1.10 SAFETY Safety as used in these Technical Specifications shall mean nuclear safety and shall encompass all systems and components that have or may have an effect on the health and safety of the general public.
1.11 FIRE SUPPRESSION SYSTEMS I.I1.1 The FlRE SUPPRESS 10N WATER SYSTEM shalI consist of water sources, pumps and distribution piping with associated sectionalizing control or isola-tion valves.
Such valves include yard hydrant valves and the first valve ahead of the water flow alarm device on each sprinkler header, hose standpipe or spray system ris,e which protect nuclear safety components.
47 1.11.2 The FIRE SUPPRESSION CARBON DIOXlDE SYSTEM shall consist of a CO2 source and distribution piping with sectionalizing control valves which protect nuclear safety components.
i Proposed Amendment No. 47 Rev. 2
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4 00 401055 A
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation l
3.14 FIRE SUPPRESSION 3.14.1 instrumentation Specification 3 14.1.1 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3 14-1 shall be OPERABLE.
3.14.1.2 With the number of instruments OPERABLE less than required b/ the Minimum Instruments OPERABLE requirement:
Within one (1) hour, the zone will be continuously occupied or a.
a fire watch patrol will be established to inspect the zone with the inoperable instrument (s) at least once per hour; and b.
Restore the Inoperable instrument (s) to OPERABLE status within fourteen (14) days; or Prepare and submit a special report to the Commission, pursuant c.
to Specification 6.9.2E, within the next ten (10) days outlining the cause of inoperability and the plans for restoring the instru-3 l
ment (s) to OPERABLE status.
3 14.2 Water System _
Speci fica tion 3 14.2.1 The FIRE SUPPRESSION WATER SYSTEM shall be OPERABLE with:
Two high pressure pumps each with a capacity of 2000 gal / min a.
with their discharge aligned to the
- ire suporession header, b.
Two-separate water supplies containing a minimum of 2,000,000 gallons each.
Automatic initiation logic for the operable fire pump.
c.
i 3.14.2.2 With less than the above required equipment, restore the Inoperable equipment to OPERABLE status within 7 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2E within the next 10 days outlining the plans and procedures to be used to provide for the loss of redundancy in'this system.
-3.14.2.3 With no FIRE SUPPRESSION WATER SYSTEM OPERABLE:
Establish a backup FIRE SUPPRESSION WATER SYSTEM within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
a.
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Proposed Amendment No. 47 Rev. 2 3-53
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RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.14.2 3 (Continued) i b.
Notify the Commission pursuant to Specification 6.9 2E outlining 2
the actions taken within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2E-within the next ten'(10) working days outlining the cause of inoperability and the plans for restorir.g the system to OPERABLE status, or d.
If a. above cannot be fulfilled, place the reactor in Hot Standby, within the next four (4) hours and Cold Shutdown within the following thirty (30) hours.
4 Proposed Amendment No. 47 Rev. 2 3-54 t
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s RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Limiting Condition for Operation TABLE 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS Zone Instrument Location Minimum Operable 11 Battery Room, Mezzanine Level 4
12 West DC Control Room, Mezzanine Level 2
13 West 480 VAC Room, Mezzanine Level 2
14 West Cable Tray Area 2
15 East Cable Tray Area 2
16 East 480 VAC Room, Mezzanine Level 2
17 East DC Control Room, Mezzanine Level 2
36 West Battery Room, Grade Level 4
37 West 4160 VAC Room 2
38 East 4160 VAC Room 2
39 East Battery Room 4
40 North Diesel Room 2
41 South Diesel Room 2
44 Reactor Coolant Pumps A and B 1
44 Reactor Coolant Pumps C and D 1
45 Electrical Penetration Area, Grade Level 2
47 North -20' Level, Auxiliary Building 2
48
-47' Level, Auxiliary Building 2
Proposed Amendment No. 47 Rev. 2 3-55 i
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's RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3 14.3 Spray and Sprinkler Systems Specification 3.14.3.1 The spray and/or sprinkler systems located in the following areas shall be OPERABLE:
a.
Control Room (Zone 3) b.
Controlled Area, Mezzanine Level (Zone 20) c.
Main Lube Oil Area, Grade Level (Zone 32) d.
Grade Level (Zone 34) e.
North Diesel Room (Zone 40) f.
South Diesel Room (Zone 41) g.
West Controlled Area, Crade Level (Zone 42) h.
East Controlled Area, Grade Level (Zone 43) 1.
South and East -20' Level (Zone 46) 3 14.3 2 a.
With a spray and/or sprinkler system inoperable establish a continual fire watch with backup fire suppression equipment for the unprotected area (s), within one (1) hour, b.
Restore the system to OPERABLE status within fourteen (14) days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2E within the next ten (10) days outlining the cause of inoperability and the plans for restoring the system to OPERABLE status.
3 14.4 C0 System
_9 Specification 3 14.4.1 The CO2= systems located in the following areas shall be OPERABLE with a minimum capacity of 66% and a minimum pressure of 275 psig in the storage tank.
a.
Zone 12 West DC Control Room Mezzanine Level b.
Zone 13 West 480 VAC Room Hezzanine Level c.
Zone 14 West Cable Tray Area d.
Zone 15 East Cable Tray Area e.
Zone 16' East.480 VAC Room Mezzanine Level f.
Zone 17 East DC Control Room Mezzanine Level g.
Zone 36 West Battery Room Grade Level-Proposed Amendment No. 47 Rev. 2 3-56
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RANCHO SECO UNIT l' TECHNICAL ~ SPECIFICATIONS
-Limiting Conditions for Operation 3.14.4.1.(continued) h.
Zor e 37 West 4160 VAC Room I.
Zone 38 East 4160 VAC Room J.
Zone 39 East Battery Room k.
Zone '40 North Diesel Room -
1.
Zone 41 South Diesel Room-3.14.4.2 a.
With a CO2 system inoperable, establish a continual fire watch with backup fire suppression equipment for the unprotected area (s), within one (1) hour.
b.
Restore the system to OPERABl.E status within fourteen (14) days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2E within the next ten (10) days, outlining the cause of inoperability and the plans for restoring the system to OPERABLE status.
3.14.5 Fire Hose Stations
~ Specification
'3.14.5.1 The fire hose stations in the following locations shall be OPERABLE:
All stations in the Auxiliary Building a.
b.
Hydrant #2 c.
Hydrant #3 d.
Hydrant at coordinates N59+17; E30+20 l
e.
Hydrant at coordinates N59+17; E32+20 l
3.14.5.2 With a hose station inoperable, route an additional equivalent -
size hose to the unprotected area from an OPERABLE hose station 1
within one (1) hour.
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1 Proposed ' Amendment No. 47 Rev. -2 3-57
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RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS l
Limiting' Conditions ifor Operation i
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~3.14.6
'Fi re ' Barrier Penet rat ion Fi re ~ Seals
' Specification =
3.14.6.1 All penetration fire barriers protecting' safety related areas shall
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be functional.
3 14.6.2 With a penetrationofire barrier non-functional, a continual. fire-watch shall be established to monitor at least one (1) side of the affected penetration within one (1) hour.
Bases OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability I's required in order to detect and. locate fires in their early stages.
P rompt
' detection of fires will reduce the potential for damage to safety rristed equip-ment and is an integral element in the overall facIIIty fire protee',on program.
In the event that a portion of the fire detection instrumentation is Inoperable, the establishment of frequent fire patrols in the affected areas is required to j
provide detection capability until the Inoperable. instrumentation is returned to service.
The OPERABILITY of :.he fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where s6fety related equipment is located. The fire
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suppression system consists of the water system, spray and/or sprinklers, CO '
2 1
and fire hose stations. The collective capability of the fire suppression systems i
is adequate to minimize 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, alter-nate backup fire fighting equipment is required 'to be made available in the affected areas until the affected equipment can be restored to service.
in the event that the fire suppression water system becomes inbperable, immediate corrective measures must be taken since this system provides the major fire
. suppression capability of.the plant.
The requirement for a twenty-four (24) hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to ' provide adequate fire suppression capability for the i
continued protection of the nuclear l plant.
The functional-. integrity of the fire barrier penetration seals ensures that-fires will. be confined or adequately. retarded from spreading to-adjacent portions of -
the ; faci l i t.y..
This ' design ' feature minimizes the possibility of a single fire rapidly involvingLseveral areas of the. facility prior to detection and extinguish-ment.
The ' fire barrier penetration seals are a passive element in the facility fire. protection program and.are subject to periodic inspections.
During periodsLof time'when the seals are not. functional, a continual: fire watch
-is'- required to be maintainedfin the. vicinity. of the affected seal until the seal
- Is restored to functional' status.
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ll RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.18 FIRE SUPPRESSION SYSTEM SURVEILLANCE 4.18.1 Instrumentation 4.18.l.1 Except for fire detection instruments inaccessible during power operation, each of the fire detection instruments in Table 3 14-1 shall be demonstrated OPERABLE at least semi-annually by a CHANNEL TEST.
4.18.1.2 Fire detection instruments inaccessible during power operation shall be demonstrated OPERABLE by performing specification 4.18.1.1 during each refueling interval.
4.18.1.3 The circuitry associated with the sprinkler water flow detector alarms in Section 3.14.3 1 shall be demonstrated OPERABLE at least semi-annually.
4.18.2 The FIRE SUPPRESSION WATER SYSTEM shall be demonstrated OPERABLE:
a.
Weekly by verifying the water supply volume.
b.
Monthly on a STAGGERED TEST BASIS by starting each pump and operating it for at least fif teen (15) minutes on recirculation flow.
c.
Annually by cycling each testable valve through one complete cycle.
d.
Semi-annually by a system flush up to each test fixture.
e.
At least once per refueling interval:
1.
By performing a system functional test which includes simulated automatic actuation of the system throughout its operating sequence and verifying that each automatic valve in the flow path actuates to its correct position.
2.
-By verifying that each pump will develop a flow of at least 2000 gpm at a system minimum pressure of 125 psig.
f.
At least once per three (3) years by performing flow tests of the system in accordance with Section ll, Chapter 5, of Fire Protection Handbook, 14th Edition published by National Fire Protection Association.
g.
Monthly by verifying that each valve (manual, power-operated or automatic) in the flow path is in its correct position as indicated by position instrumentation.
Proposed Amendment No. 47 Rev. 2 r
4-58
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T RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS
. Surveillance Standards 4.18.'2 h.
The fire pump diesel engine shall be demonstrated OPERABLE:
1.
Monthly by verifying:
a.
The fuel storage tank contains at least 250 gallons of fuel, and b.
The diesel starts from ambient conditions and operates for at-least 20 minutes.
2.
At least once per refueling interval by:
a.
Subjecting the' diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service, and b.
Verifying the diesel starts from ambient conditions on the auto-start signal and operates for > 20 minutes 4
while loaded with fire pump.
3 Quarterly by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, is w! thin the acceptable limits specified in Table 1 of ASTM-D975-74 with respect to viscosity, water content and sediment.
I.
The fire pump diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLE:
1.
Weekly by verifying that:
a.
The electrolyte level of -ach battery is above the plates, and b.
Theoverallbatteryvoltageisi24 volts.
2.
Quarterly by verifying that the specific gravity is appro-priate for continued service of the battery.
3 At least once per refueling interval by verifying that:
a.
The batteries and battery racks show no visual indica-tion of physical damage or abnormal deterioration, and b.
The battery-to-battery and terminal connections are Lclean, tight, free of cors ston and coated with anti-corrosion material.
l-Proposed Amendment No. 47 Rev. 2
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards F
4.18.3
'The spray and/orysprinkler systems specified 'in Section 3.14.3 1 shall. be -demonstrated to be OPERABLE:
a.
l Annually by' cycling each testable valve through'one complete cycle.
b.
Each REFUELING INTERVAL:
l.:
By: performing a. system functional test which includes simu-lated automatic actuation of the system' and verifying that the automatic valves in the flow path actuate to their correct positions; and 2.
By inspection of spray and/or sprinkler headers to verify cheir integrity; and c.
By inspection of each nozzle and/or sprinkler to verify no blockage.
4.18.4 The CO2 system shall be demonstrated OPERABLE:
a.
Weekly by verifying the CO2 storage tank level and pressure.
b.
Each refueling interval by verifying the system electro manual-pilot' valves and associated ventilation dampers actuate automati-cally and manually to a simulated actuation signal. A flow test shall be made to verify ficw from each nozzle.
4.18.5 Each fire hose station shall be verified to be UPERABLE:
i a.
Monthly by visual inspection of the station to assure all equip-ment'is available.
1 b.
Each refueling interval inspect and replace all gaskets in the couplings that are degraded.
f open hose station valves to l
Once per three (3) years, partiati c.
verify valve operability and no valve blockage.
d.
Once per three (3) years by removing and replacing all hose with equivalent.NFPA tested and approved hose.
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4.18.6 Penetration fire. barriers shall be verified to be functional by a j
visual inspection:
a.
At least once each' refueling interval; and b.
Prior to declaring a fire-penetration seal functional following repairslor maintenance.
Proposed Amendment No. 47 Rev. 2 4-60
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.t 6.0-ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent shall be -responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.
FACILITY STAFF 6.2.2 The facility organization shall be as shown on Figure 6.2-2 and:
a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the Control Room when fuel is in the reactor.
c.
At least two licensed Operators shall be present in the Control Room during reactor startup, scheduled reactor shutdown and during recovery f rom reactor trips.
d.
An Individual qualified in radiation protection procedures shall be on site when fuel is in the reactor, e.
ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
A Fire Brigade of 3 members shail be maintained on the site at all times. This excludes 2 members of the minimum shif t crew necessary for safe shutdown of the plant and any personnel required for other 4/-
essent!:: functions during a fire emergency.
1 Proposed Amendment No. 47 Rev. 2 6-1 7
BOARD OF DIRECTORS d
SECRETARY TREASURER ATTORNEY ACCOUNTANT INDEPENDENT CONSULTANTS MANAGEMENT PERIODIC SAFETY AUDIT GENERAL MANAGER SAFETY REVIEW OF RANCHO SECO OPERATIONS COMMITTEE I
I I
I CONSUMER 1
PERSONNEL RELATIONS LEGAL STAFF DEPARTMENT DEPARTMENT l
AGM*
AGM*
AGM* (**)
l47 CONTROLLER OPERATIONS CHIEF ENGINEER I
SYSTEMS & PROCEDUfES QUALITY STAFF INTERNAL AUDITING ASSURANCE DISTRIBUTION ACCOUNTING CONSTRUCTION ENGINEERING DEPARTMENT DEPARTMENT DEPARTMENT DATA DISTRIBUTION HYDRO PROCESSING PLANNING OPERATIONS DEPARTMENT DEPARTHENT DEPARTMENT GENERAL DISTRIBUTION NUCLEAR SERVICES OPERATION OPERATIONS DEPARTHENT DEPARTMENT DEPARTMENT PURCHASES CUSTOMER GENERATION
& STORES SERVICES ENGINEERING DEPARTMENT DEPARTMENT DEPARTMENT 1
- AGM - Assistant General Manager
- Responsible for Fire Protection Program l47 I
F GURE 6.2-1 SMUD ORGANIZATION CHART RANCHO SECO UNIT I TECHNICAL-SPECIFICATIONS
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Proposed Amendment No. 47 Rev. 2 l
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PLANT **
47 SUPERINTENDENT ADMINISTRATIVE TECHNICAL STAFF ASSISTANT
- ASST. SUPT.
ASST. SUPT.
MAINTENANC.E TECHNICAL NUCLEAR PLANT SyPERVISOR SUPPORT
- OPERATIONS (SL)
- SHIFT M AIN NNANCE SUPERVISOR (SL)
PERSO h'NEL SR. CONTROL
{
ROOM OPERATORS (L) i t
SR. POWER PLANT CHEMICAL RADIATION INSTRUMENT CONTROL SUPERVISOR flUPERVISOR (NUCL R / MECHANIC AL)
CONTROL ROOM OPERATORS (L)
I i
CHEMISTRY RADIATION INSTRUMENT CONTROL PERSONNEL PERSONNEL l
AUXILIARY OPERATORS i
SL SENIOR OPERATOR LICENSE L - OPERATOR LICENSE EQUIPMENT
- - ROUTINE REPORTING REQUIRE-ATTENDENTS MENTS ON PERSONNEL CHANGI*
- -Responsible for Fire Protection Program l47 i
FIGURE 6.2-2 PLANT _ORGANI,ZATION CHART RANCHO SECO UNIT 1 l
TECHNICAL SPECIFICATIONS l
Proposed Alaendment No. 47 Rev. 2 l
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f ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the operating staff shall meet or. exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the operating staf f shall be e-intained under the direction of the Training Supervisor and s..all meet or exceed the requirements and recommenda-tions of Section 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 the Safety Technician and shall meet or exceed 47 the requirements of Section 27 of the NFPA Code - 1976, except refresher classroom training shall be on a quarterly schedule.
6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)
FUNCTION 6.5.1.1 The Plant Review Committee shall function to advise the Plant Superintendent on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Plant Review Committee shall be composed of the:
Cnalrman: Technical Assistant Member:
Assistant Superintendent Nuclear Plant Operations Member:
Assistant Superintendent Technical Support Membe r:
Maintenance Supervisor Member:
Chemical and Radiation Supervisor Other members as the Plant Superintendent may appoint from time to time.
Proposed Amendment No. 47 Rev. 2
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ADMINIST,RATIVE CONTROLS AUDITS 6.5.2.8 Audits of facIIIty activities shall be performed under the cognizance of the -MSRC.
These' audits shall encompass:
a.
The 'conformance of facility operation to all provisions contained within the Technical Specifications and applicable licensed conditions at least once per year.
b.
The performance, training and qualifications of the entire facility staff at least once per year.
c.
The result of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.
d.
The performance of all activities required by the 0uality Assurance' Program to meet the criteria of Appendix "B",10 CFR 50, at least once per two years.
The Facility Emergency Plan and implementing procedures at least e.
once per two years.
f.
The Facility Security Plan and implementing procedures at least once per two years.
g.
Any other area of facility operation considered appropriate by by the MSRC or the General Manager.
h.
Compliance with fire protection requirements and implementing procedures at least once per two (2) years.
I.
An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite 47 licensee personnel or an outside fire protection firm.
j.
An Inspection ana audit of the fire protection and loss prevention prsgram shall be performed by an outside qualified fire consnitant at intervals no greater than 3 years.
AUTHORITY 6.5.2 9 The MSRC shall report to and advise the General Manager on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.
Proposed. Amendment No. 47 Rev. 2 6-9
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e ADMINISTRATIVE CONTROLS.
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6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
5 a.
The provisions of 10 CFR 50.36 (c) (1) (i) shall be complied with immediately.
b.
The Safety Limit violation shall be reported to the Plant Supe ri ntendent, the Chairman of the MSRC and to the Commission immediately.
c.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PRC.
This report shall describe (1)-
applicable circumstances 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 Violation Report shall be submitted to the Commission, the MSRC and the Plant Superintendent within ten (10) days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November 1972.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fi re Protection Procedures imp.lementation.
47 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PRC and approved by the Plant Superintendent prior to-Implementation and reviewed periodically as set forth in each document.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
2 a.
The intent of the original procedure is not altered.
Proposed Amendment No. 47 Rev. 2 6,,
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, ADMINISTRATIVE CONTROLS 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 on the unit affected.
c.
The change is documented, reviewed by the PRC, and approved by the Plant Superintendent within 7 days of implementation.
f.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 Information to be reported to the Commission, in addition to the reports required by Title 10, Code of Federal Regulations, shall be in accordance with the Regulatory Position in Revision 4 of Regulatory Guide 1.16, " Reporting of Operating information - Appendix "A" Technical Specifications".
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Regulatory Operations Regional Of fice wi thin the time period specified for each report.
These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
A.
Startup Report A summary report of uni t startup and power escalation testing and an evaluation of the results from these test programs shall be submitted within 60 days following commencement of commercial power operation.
The test results shall be compared with design predictions and specifications.
B.
A Reactor Building structural integrity report shall be submitted within 90 days of completion of each of the following tests covered by Technical Specification 4.4.2 (the integrated leak rate test is covered in Technical Specification 4.4.1.1).
.1 Annual Inspection
.2 Tendon stress surveillance 3
End anchorage concrete surveillance l
.4 Liner plant surveillance C.
Inservice inspection Program.
D.
(Reserved for Proposed Amendment No. 43}
47 E.
Status of inoperable fi re protection equipment.
Proposed Amendment No. 47 Rev. 2 6-12