ML19261C363
| ML19261C363 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 02/26/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19261C360 | List: |
| References | |
| NUDOCS 7903220332 | |
| Download: ML19261C363 (10) | |
Text
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'3 umirs nst NU OLExF. REGU_%~ O A i c 3.a!.ilc31CIJ j
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WASHINGTON, D. C. 20555 i
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PORTLAND GENERAL ELECTRIC COMPAR THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. NPF-1 1.
The Nuclear Regulatory Conmission (the Commission) has found that:
A.
The application for amendment by Portland General Electric Company, the City of Eugene, Oregon, Pacific Power an~d Light Company (the licensee) dated August 10, 1977 as supple-mented and amended September 1,1978, and January 19, 1979 complies with the standards and requirements of the Atomic Energy Act of 19t4, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to tne Tecnni;al Specifications as ir.dicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility License No. GF-1 is hereby amended to read as follows:
7903220 3 3 1
. "(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 37, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, except as noted in para -
graph 2.C.(10) below."
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: February 26, 1979
ATTACHMENT TO LICENSE AMENDMENT NO. 37 FACILITY OPERATING LICENSE NO. NPF-1
_ DOCKET NO. 50-344 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness, ges VII XIII 3/4 7-32 (added) 3/4 7-33 (added)
'3/4 7-34 (added) 3/4 7-35 (added) 3/4 7-36 (added)
B 3/4 7-6 B 3/4 7-7 (added)
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS Pace SECTION 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........
3/4 7-12 3/4.7.3 COMPONENT COOLI NG WATER SYSTEM.........................
3/4 7-13 3/4.7.4 S E RV I C E WAT E R S Y ST EM...................................
3/4 7-15 3/4.7.5 U LT IMAT E H EAT S I N K.....................................
3/4 7-17 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM..............
3/4 7-18 3/4.7.7 SEALED SOURCE CONTAMINATION............................
3/4 7 -21 3/4.7.8 FIRE SUPPRESSION SYSTEMS 3/4 7 -23 Fire Suppression Water System.
Sprinkler Systems......................................
3/4 7 -27 F i re Ho s e S ta ti o ns.....................................
3/4 7-29 3/4.7.9 PENETRATION FIRE BARRIERS..............................
3/4 7 -31 3/4.7.10 HYDRAULIC SNUBBERS.....................................
3/4 7 -32 l
3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating..............................................
3/4 8-1 S h u td ow n...............................................
3/48-5 3 /4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Di stribu ti on - Operati ng..........................
3/48-6 A.C. Di s tri buti on - Shu td own...........................
3/48-7 D.C. Di stri bu tion - Op erati ng..........................
3/48-8 D.C. Di s tri buti on - Shu tdown...........................
3/4 8-10 TROJAN-UNIT 1 VII Amendment No. JS, 37
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 B ORON CON CE NT RAT I ON....................................
3/49-1 3/4.9.2 INSTRUMENTATION........................................
3/4 9-2 3/4.9.3 DECAY TIME.............................................
3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS......................
3/4 9-4 3/4.9.5 COMMUNICATIONS.........................................
3/4 9-5 3/4.9.6 MANIPULATOR CRANE OPERABILITY..........................
3/4 9-6 3/4.9.7 CRANE TRAVEL - FUEL BUILDING...........................
3/4 9-7 3/4.9.8 COOLANT CIRCULATION....................................
3/4 9-8 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM...............
3/4 9-9 3/4.9.10 WATER LEVEL-REACTOR VESSEL.............................
3/4 9-10 3/4.9.11 STCRAGE POOL WATER LEVEL...............................
3/4 9-11 3/4 9.12 SPENT FUEL POOL EXHAUST SYSTEM.........................
3/4 9-12 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN........................................
3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS..
3/4 10-2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION-REACTOR CRITICALITY....
3/4 10-3 3/4.10.4 PHYSICS TESTS..........................................
3/4 10-5 3/4.10.5 NATURAL CIRCULATION TESTS..............................
3/4 10-6 TROJAN-UNIT 1 VIII Amendment No.18
INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE...........................................
B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE /TEMERATURE LIMITATION.......... B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM.......................... B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM...................................,
B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK......................................
B 3/4 7-4 3/4.7.6 CONTROL ROOM V ENTI LATION SYSTEM......................... B 3/4 7-5 3/4 7.7 SEALED SOURC E CO NTAMINATION............................. B 3/4 7-5 3/4.7.8 FIRE SUPPRESSION SYSTEMS................................ B 3/4 7-5 3/4.7.9 P ENETRATION F I RE B ARRI ERS............................... B '/4 7-6 3 /4.7.10 HYDRAULI C S NUB B ERS...................................... B ?/4 7-6 l
3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.
S OU RC E S........................................... 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 BORON CONCENTRATION.....................................
B 3/4 9-1 3/4.9.2 INSTRUMENTATION.........................................
B 3/4 9-1 3/4.9.3 DECAY TIME..............................................
B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING P ENETRATIONS....................... B 3 3/4.9.5 COMMUNICATIONS..........................................
B 3/4 9-1 TRGJAN-UNIT l XIII Amendment No. JS, 37
INDEX BASES SECTION PAGE 3/4.9.6 MANI PU LATOR CRANE OPERABILITY......................... B 3/4 9-2 3/4.9.7 C RANE TRAVEL - FUEL BU ILDING.......................... B 3/4 9-2 3/4.9.8 C OO LANT C I RCU LAT I ON................................... B 3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM..............
B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND STORAGE P00L..................................................
B 3/4 9-2 3/4.9.12 SPENT FUEL POOL EXHAUST SYSTEM........................
B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 S HUT DO WN MARGI NS...................................... B 3/410-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS. B 3/410-1 3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS-REACTOR C RIT ICAL ITY............................................ B 3/4 10-1 3/4.10.4 PHYSICS TESTS.........................................
B 3/4 10-1 3/4.10.5 N ATU RAL CIRCULATION TESTS............................. B 3/4 10-1 TROJAN-UNIT 1 XIV
PLANT SYSTEMS 3/4.7.9 PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION 3.7.9 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-functional, 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 appitcable.
SURVEILLANCE REQUIREMENTS 4.7.9 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 declaring a penetratio" fire barrier functional following repairs or maintenanc.
TROJAN-UNIT 1 3/4 7-31 Amendment No.18
PLANT SYSTEMS 3/4.7.10 HYDRAULIC SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.10.1 All hydraulic snubbers listed in Table 3.7-5 shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more hydraulic snubbers inoperable, replace or restore the inoperable snubber (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within___.
the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURV_EILLANCE REQUIREMENTS 4.7.10.1 Hydraulic snubbers shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program:
a.
Each hydraulic snubber with seal material fabricated from ethylene propylene or other materials demonstrated compatible with the operating environment and approved as such by the NRC, shall be determined OPERABLE in accordance with the inspection schedule of Table 4.7-4 by a visual inspection of the snubber. Visual inspections of the snubbers shall include, but are not necessarily limited to, inspection of the hydraulic fluid reserviors, fluid connections, and linkage connections to the piping and anchors.
Initiation of the Table 4.7-4 inspection schedule shall be made assuming the unit was previously at the 18 month inspection interval.
b.
Each hydraulic snubber with seal material not fabricated from ethylene propylene or other materials demonstrated compatible with the operating environment shall be determined OPERABLE at least once per 31 days by a visual inspection of the snubber.
Visual inspections of the snubbers shall include, but are not necessarily limited to, inspection of the hydraulic fluid reservoirs, fluid connections, and linkage connections to the piping and anchors.
TROJAN-UNIT 1 3/4 7-32 Amendment No. 37
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
At least once per 18 months during shutdown, a representative sample of at least 10 hydraulic snubbers or at least 10% of all snubbers listed in Tatle 3.7-5, whichever is less, shall be selected and functionally tested to verify correct piston movement, lock up and bleed. Snubbers greater than 50,000 lb capacity may be excluded from functional testing requirements.
Snubbers selected for functional testing shall be selected on a rotating basis. Snubbers identified as either "Especially Difficult to Remove" or in "High Radiation Zones" may be exempted from functional testing provided these snubbers were demonstrated OPERABLE during previous functional tests.
Snubbers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation. For each snubber found inoperable during these functional tests, an additional minimum of 10% of all snubbers or 10 snubbers, ohichever is less, shall also be functionally tested until no mc*e failures are found or all snubbers have been functionally testad.
TROJAN-UNIT 1 3/4 7-33 Amendment No. 37
-4y TABLE 3.7-5 SAFETY RELATED HYDR /JLIC SNUBBERS
LOCATION #
SYSTEM-EQUIPMENT INACCESSIBLE ZONE DURING SHUTDOWN **
TO REHOVE
~
(A OR I)
(Yes or No)
(Yes or Po)
SS-81 Containment /
No Yes 81-3S76/8EJ from Steam Generator B SS-86 Containment /
No Yes 81-3N63/8EJ from Steam Generator A SS-88 Containment /
No Yes 91-3S76/18WJ from Steam Generator C SS-92 Containment /
No Yes 91-3N63/17WJ from Steam
{
Generator D
[
S/G A-1 Upper Steam Generator A I
Yes Yes S/G A-7 Lower Steam Generator A I
Yes Yes S/G A-10 Upper Steam Generator A I
Yes Yes S/G A-13 Lower Steam Generator A I
Yes Yes S/G B-5 Lower Steam Generator B I
Yes Yes S/G B-12 Upper Steam Generator B I
Yes Yes S/G B-14 Lower Steam Generator B I
Yes Yes k
S/G B-15 Upper Steam Generator B I
Yes Yes Eil
?.
E.
Y g
TABLE 3.7-5 (Continued) 2y SAFETY RELATED HYDRAULIC SNUBBERS
LOCATION #
SYSTEM-EQUIPMENT INACCESSIBLE ZONE DURING SHUTDOWN **
TO REMOVE (A OR I)
(Yes or No)
(Yes or No)
S/G C-2 Upper Sterm Generator C I
Yes Yes S/G C-4 Lower Steam Generator C
'I Yes Yes S/G C-11 Lower Staam Generator C I
Yes Yes S/G C-16 Upper S'.eam Generator C I
Yes Yes S/G D-3 Lower Steam Generator D I
Yes Yes S/G D-6 Lower Steam Generator D I
Yes Yes S/G D-8 Upper Steam Generator D I
Yes Yes S/G D-9 Upper Steam Generator D I
Yes Yes M
[
Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-5 g
provided that a revision to Table 3.7-5 is included with the next License Amendment request.
Modifications to this column due to cht.nges in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.7-5 is included t'ith the next License Amendment request.
Location Code: Containment /81-3576/8EJ translates to: Containment. El. 81' (to closest foot), 3' South of Col. Line 76, 8' East of Col. Line J.
Y air an l
l
a TABLE 4.7-4 Rj_
HYDRAULIC ~ SNUBBER INSPECTION SCHEDULE
.2 NUMBER OF SNUBBERS FOUND INOPERABLE NEXT REQUIRED DURING INSPECTION OR DURING INSPECTION INTERVAL
- INSPECTION INTERVAL **
0 18 months + 25%
1 12 months T 25%
2 6 months T 25%
3 or 4 124 days T 25%
5, 6 or 7 62 days T 25%
>8 31 days
+ 25%
M T'
1X T
Snubbers may be categorized into two groups, " accessible" and " inaccessible." This categorization shall be based upon the snubber's accessibility for inspection during reactor operation. These two groups may be inspected independently according to the above schedule.
The required inspection interval shall not be lengthened more than one step at a time and the provisions of Specification 4.0.2 are not applicable.
g 8-2 ti
PLANT SYSTEMS BASES 3/4.7.6 CONTROL ROOM VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ensures that
- 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design pro-visions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consisten with the requirements of General Design Criteria 19 of Appendix "A",10 CFR 50.
l 3/4.7.7 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the source material.
The limitations on removable contamination for so.urces requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. Leakage of sources excludeo from the requirements of this specification represent less than one maximum permissible body burden for total body irradiation if the source material is inhaled or ingested.
3/4.7.8 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, sprinklers and fire hose stations. The collective capability of the fire suppression systems 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 systtms are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
TROJAN-UNIT 1 B 3/4 7-5 Amendment No. 78, 26
PLANT SYSTEMS BASES In the event the fire suppression water system becomes inoperable, imediate corrective measures must be taker since this system provides the major fire suppression capability of tl' plant. The requirement for a twenty-four hour report to the Comissu ovides for prompt evaluation of the acceptability of the corrective mes-to provide adequate fire suppression capability for the continued prostion of the nuclear plant.
3/4.7.9 PENETRATION FIRE BARRIERS g
The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguish 1ent. The penetration fire barriers are a passive element in the fat.'iity fire protection program and are subject to periodic inspections.
During periods of time when the barriers are not functional, a con-tinuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status.
3/4.7.10 HYDRAULIC SNUBBERS The hydraulic snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads. The only snubbers excluded from this inspection program are those installed on nonsafety related systems and then only if their failure or failure of the system on which they are installed, would have nc adverse effect on any safety related system.
The inspection frequency applicable to snubbers containing seals fabricated from materials which.have been demonstrated compatible with their operating environment is based upon maintaining a constant level of snubber protection. Therefore, the required inspection interval varies inversely with the observed snubber failures. The number of inoperable snubbers found during an inspection of these snubbers detemines the time interval for the next required inspection of these snubbers.
Inspections performed before that interval has elapsed may be used
!!awever, the as a new reference point to determine the next inspection.
results of such early inspections perfomed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required invection interval. Any inspection whose results require a shorter inspeccion interval will override the previous schedule.
TROJAN-UNIT 1 B 3/4 7-6 Amendment No. 78, 37
PLANT SYSTEMS BASES To provide further assurance of snubber reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals. These tests will include stroking of the snubbers to verify proper piston movernent, lock-up and bleed.
Observed failures of these sample snubbers will require functional test-ing of additional units. To minimize personnel exposures, snubbers installed in areas which have high radiation fields during shutdown or in especially difficult to remove locations may be exempted from these functional testing requirements provided the OPERABILITY of these snubbers was demonstrated during functional testing at either the completion of their fabrication or at a subsequent date.
TROJAN-UNIT 1 B 3/4 7-7 Amendment No. 37
.