ML19330B773
| ML19330B773 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/25/1980 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19330B763 | List: |
| References | |
| ISSUANCES-SP, TAC-11299, TAC-13152, NUDOCS 8008050482 | |
| Download: ML19330B773 (21) | |
Text
.
UNITED sTATi$
(^y g
NUCLEAR REGULATORY COMMISSION
(,/ 3 g
w AssiNo TON, D. C. 20555
%,[.
,/
PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMErlT TO FACILITY OPERATING LICENSE Amendment No. 47
'e License No. NPF-1 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The proposed modifications of the Building Complex should be permitted in accordance with the amend-ment to the Operating License set forth below and subject to the terms and conditions therein; 1
B.
There is reasonable assurance that operation of 1
the plant, including the activities authorized by the operating license, as thus amended, and
\\
including the terms and conditions set forth below, can be conducted without endangering the health and safety of the public; C.
There is reasonable assurance that operation of the plant, including the activities authorized by the operating license, as thus amended, and including
?3008050y$h
the terns and conditions set forth below, will,be
. conducted in compliance with the Atomic Energy Act of 1954, as amended, and the Commission's regulations; 3
D.
The. issuance of this operating license amendment as set forth' below will not be inioical to the common defense and s'ecurity or to the health and safety of the public; E.
The issuance of this amendment is in accordance eith 10 CFR Part 51 of the Commistion's regula-tions and all applicable requirements have been satisfied; and F.
The proposed modifications will satisfy the Order of May-26, 1978 by bringing the Control Building into substantial compliance with Technical Specifi-
~
cation 5.7.1 of the operating license, and restoring the intended design margins of Technical Specifica-tion 5.7.1 such that (a) the Control Building has a capacity to withstand a 0.15g OBE using 27. damping as required by FSAR Table 3.7.1; (b) the Control 3nilding OBE capability of O.15g and SSE capability of 0.23g are met using a yield strength for reinforcing steel.of 40,000 psi; and (c) the casonry. portions of the Control Building walls cc= ply with the U3C requirements for reinforced grouted masonry for inplane loading.
2.
Accordingly, Facility Operating License No.
NPF-1 is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, by amending paragraph 2.C.(2), and by adding paragraph 2.C.(12) to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
are hereby incor,porated in the license.
The licensee shall operate the facility in accordance with'the Technical Specifications, except as noted in paragraphs 2.C.(10) through 2.C.(12) below.
(12) Control Building Modifications.
The Licensee
_; authorized to and shall proceed with modi-fications to the control Building in order to restore substantially the originally intended design margins.
The modification program shall be accomplished in accordance with PGE-1020, " Report on Design Modifications for the Troj an Control Building'.', as revised through Revision No. 4, and as supplemented by PGE Exh. 27 (Licensee's Testirony ("Broehl, el al.")
e 0
4-on Matters Other Than Structural Adequacy of the-Modified Complex, M&rch 17, 1980).
Any
\\
deviations or changes from the foregoing documents shall be accomplished in accordance with the provisions of 10 CFR part 50.59.
The Control Building modification program shall further be subject to the following:
(a) The modification program shall be completed not later than 12 mohths from the date of this amendment, provided 'however that such completion date may be extended by the Director of Nuclear Reactor Regulation upon a showing that the completion of the modi-fication program is necessarily delayed by circumstances wholly beyond the control of Licensee.
When all modifications have been completed, license condition 2.C. (10),
relating to interim operation pending completion of codifications, is cancelled.
(b) For the installation of steel plate-No. 8, the plant shall be in the cold shutdown condition (Modes 5 or 6) from the time that the plate is lifted from the transporter at Elevation 45 feet until the plate has been secured with 48 inches of weld to the N _
e em me+ me, m.
9,,,,,,
previously installed plates and attached to the wall with five bolts made snug.
During the installation of p1' ate No. 8, both trains of safety-related equipment recessary for caintenance of a cold shutdown condition shall be operable.
Prior to the installa-tion,. Diesel Generator A shall be started and proper operability verified.
(c) Solid steel cable tray covers shall be installed over cable trays in work areas where cable damage is possible from accidental dropping of steel plate washers during their installation.
(d) A fire watch patrol shall be established whose sole responsibility shall be to watch for fires at the plant and which shall nake at least hourly inspections at all safety-related areas where combustible materials (e.g., wood framing, planking, plastic, etc.) related to the modification work must re=ain in the work area (not required for areas in which a continuous fire watch is present).
Such hourly
-inspections shall include direct visual S*
observations'of all co=bustible cateri.als added to such safety-related areas.
(e) Scaffolding and timber planking shall be installed against the R line wall in the Cabl'e Spreading Room during the installa-tion of the steel plate washers at each location Where a potential plate washer drop onto'a cable tray could exceed three feet.
The planking shall,te placed and constructed to limit the maximum ~ height of a dropped washer to three feet or less.
(f) Any construction work in the diesel generator combustion / ventilation air pathway which could potentially generate i
dust, dirt or debris shall be temporarily halted when any diesel generator is in operation.
(g) In the event that either the Shift Super-visor or NRC Resident Inspector determines that construction noise is resulting in noise levels in the Control Room of such magnitude as to interfere with normal communications, the construction activity shall be halted until alternate means are devised (e.g., lighter weight tools, other I
4 d.
..-r
- ~ -..
-~7
=eans of concrete / block removal, etc.) to proceed with the wo'rk with acceptably reduced Control Room noise level.
(h) In the event that the NRC Resident Inspector detdrmines that the conr.truction activity
{
in the Electrical-Auxiliari s Room or Control Room is generating excessive dust, dirt or debris or the use of water is being inproperly contro11,ed, construction work shall be halted until appropriate corrective measures have been taken.
(i) During periods when safety-related equip-ment is vulnerable to either external missiles or missiles from construction work (e.g., j ackhammers), Licensee shall provide suitable barriers to protect against such exposure or place the plant in cold shutdown during such work.
(j) During hole drilling in the east and west walls of the Control Building, personnel shall be st'tioned on the opposite side a
of the wall from the driller to monitor the drill penetration.
Continuous voice ccm:nnications shall be maintained between the drill operator and the monitor.
y-
(k) Fire blankets (Claremont Weld Shield 800-24 or.FabriCote 1584-white) shal'1 be used over all cables in areas where Cadwelding; welding or cutting will be performed.
(1) The Battery Roon exhaust duct shall not be
~
disabled unless an alternate, equivalent means,of Battery Room ventilation is first provided.
(m) Prior to the installation of plates 1 through 6, a temporary energy absorber
.shall be installed to preclude exceeding the all'owable compressive strength of the underlying concrete in the event of an accidental plate drop.
(n) An energy absorber shall be placed on plate 4 prior to the installation of plate 7.
(o) A one-inch-thick, precrushed, stabilized Hexcel pad and timber cribbing shall be used on top of the previously inctalled p'f.ates for energy absorption during the installation'of. plate 8.
(p) The work area at 41 R (Elevation 65 feet) shall be protected by a dust-tight flame-retardant enclosure.
Similar protective 4 e un e a
=.. -..o
,.,m,,,,,,,,
_9.
measures shall be applied at any other
~
locations in the Electrical Auxiliaries Room or Control Room where wall removal is necessary.
(q) - ?ipihg systems, equipment and components within the Control / Auxiliary / Fuel. Building Complex required for safe shutdown or to
=aintain off-site doses from accidents to within 10 CFR Part 100 g,uideline values shall remain sei smically-qualified for darthquakes up to and including the SSE throughout all structural modification work.
Any changes to piping systecs, equipment and components necessary to ensure that this condition is met shall be perforced before the structural modifi-cations are made.
(r) The Licensee shall perform three grout tests for each size and orientation of reinforcing steel (rebar) to be grouted into the existing walls and hole size (considerin5 both depth and radius) in which they-are to be grouted prior to proceeding with construction (grouting of rebar), or the Licensee shall perform three grout tests using the maxicum bar 1
1 1
i
size-in the'mininum dic ster. hole size and embedment' length for each orientation (i.e., horizontal, vertically <up and down).
These tests shall be designed'to demonstrate that the yield strength of the rebar can. be developed by the grout.
If any test result is unsuccessful, the NRC shall be notified.
(s) Should a drop of plates 7 or 8 occur onto the plates below, the Licensee shall report the circumstances to NRC immediately.
Plates 1 through 6 shall be removed and damage inspection made unless it can be substantiated to the satisfaction of the NRC Staff that plate removal is unnecessary.
(t) Exposure of embedded steel columns in the Control Buildin, walls during the modifi-cation work shall be subj ect to the following restrictions:
(1)
Between Elevation 45 feet and Eleva-tion 65 feet, coluan 41 Q may not be i
exposed unless columns 41 R and 41 N are embedded in the original vall or encased in concrete that ha's attained a compressive strength of 2,000 psi; likewise.colunns 41 R and 41 N cay m
-w p-
- w ~
c
~
not be exposed unless colu=n 41.Q is ambedded or encased by 2,000 psi concrete.
(
(2)
Colu=ns 55 N' and 55 Q may not be
' exposed concurrently, and the second
.~f these may not be exposed before the concrete encasing the first has attained a corpressive strength of 2,000 psi.
(3)
No colurns may be exposed above Elevation 65 feet before concrete in the new N' wall has attained a compressive strength of 3,500 psi and the new concrete in the N and R walls below Elevation 65 feet has attained a corpressive strength of 2,000 psi.
(4)
Between Elevation 65 feet and Eleva-tion 77 feet, columns 41 N and 46 N may not be exposed unless colu=ns 41 R and 46 R are e= bedded in the original wall or encased in concrete that has attained a compressive strength of 2,000 psi: likewise coluans 41 R and 46 R cay not be exposed unless columns m
4 41 N and.46 N are embedde'd in the original wall 'or encased in 2,000 psi concrete.
'(5)
Above Elevation 77 feet, column 41 R
- may not be exposed unless the new concrete in R line wall below that glevation has attained 2,000 psi compressive strength, and columns 41 N and 46 N are er. bedded in the original wall and/or encased in 2,000 psi concrete.
(u) Prior to the installation of plate 7, the concrete behind plates 1-4 shall have attained a compressive strength of 3,500 psi.
Prior to the installation of plate 8, the concrete behind plates 1-7 shall have attained a compressive strength of 3,500 psi.
(v) In any plane of a wall at any given floor elevation, the wall area removed from drilling pursuant to the proposed modifi-cations,-including holes abandoned because rebar was encountered and not filled with grout that has reached design strength, shall be limited to 67..
l l
+
n
,r.-.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION g/
i e
ide u,'irec or Division o Licensing
Attachment:
Changes to the Technical Specifications Date of-Issuance:
July 25, 1980 L
y 7-
~
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 47 TO FACILITY OPERATING LICENSE N0. NPF-1 DOCKET NO. 50-344' Revise Appendix A as follows:
Remove Pages Insert Pages VII (Index)
VII XIII XIII 3/4 7-37 3/4 7-38 B 3/4 7-8 5-6 5-6 5-6a i
i i
' INDEX-LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 4
SECTION Page 4
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........3/4 7-12 3/4.7.3-COMP 0NENT. COOLING ' WATER SYSTEM.........................
3/4 7-13 3/4.7.4' ' S E RV I CE WATE R SY ST EM..................................
3/4 7-15 i
3/4.7.5 U LT IMAT E H E AT S IN K.....................................
3/4 7-17 d
3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM..............
3/4 7-18 l
3/4.7.7 SEALED SOURCE CONTAMINATION..........................
3/4 7 -21 l
3/4.7.8. ' FIRE SUPPRESSION SYSTEMS
[
Fi re Suppres si on Wa ter System..........................
3/4 7 -23 3/4 7 -27 Sprinkler Systems......................................
Fi re Hos e Sta ti o ns.....................................
3/4 7-29 3/4.7.9 PENETRATION FIRE BARRIERS..............................
3/4 7-31 j
3/4.7.10 HYDRAULIC SNUBBERS.....................................
-3/4 7-32
}
3/4.7.11 l CONTROL BUILDING MODIFICATION CONNECTION B0LTS.........3/4 7-37 l
l-I-
3/4.8 l ELECTRICAL POWER SYSTEMS 4
I j
3/4.8.1 A.C. SOURCES 0perating..............................................
3/48-1 i
S h u td ow n...............................................
3/48-5 2
l 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS h
'A.C.. Di str ibu ti on - Oper ati ng..........................
3/48-6
- A. C. Di s tri b u t i on - Sh u td own...........................
3/48-7
~
D.C. Di s tri bu tion - Operati ng..........................
3/48-8
. D. C. Di s tri bu ti on - Sh u td own...........................
3/4 8-10 e
'l TROJAN -UNIT ~ 1 VII Amendment No. JS, //,47 1
-INDEX BASEF-SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBI 2 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 VENTILATION SYSTEM.........................
B 3/4 7-5 3/4 7.7 SE ALED SOURC E CONTAMINATION............................. B 3/4 7-5 3/4.7.8 FIRE SUPPRESSION SYSTEMS................................ B_3/4 7-5 3/4.7.9 - PENETRATION FIRE B ARRIERS............................... B 3/4 7-6 3/4.7.10 HYDRAUL I C SNUBB ERS......................................
B 3/4 7-6 3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION B0LTS..........
B 3/4 7-8
{
3/4.8 ELECTRICAL POWER SYSTEMS 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 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 PENETRATIONS....................... B 3/4 9-1 3/4.9.5 COMMUNICATIONS..........................................
B 3/49 -1 TROJAN-UNIT 1 XIII Amendment No. IS, )/, 47
PLANT SYSTEMS l
l3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION BOLT 5 *
'! IMITING CONDITION FOR CPERATION L
I l
3.7.11 The structural adequacy of the through-wall bolts used to tie rein-forced concrete and steel plate to the Control Building west and east walls shall be maintained at a level consistent with the ' acceptance criteria in i
Speci fica tion 4.7.11.1..
1 APPLIC ABILITY:
ALL MODES i
!l ACTION:
With the structural adecuacy of the bolts not confonning to the above j' a.
requirements, restore the structural adequacy of the bolts to within the limits within 14 days.
il b. If the strtetural adequacy of the bolts does not confora to the above i
requirements, report the degradation within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and prepare and
! l[
submit a spacial report pursuant to Specificatiot 6.9.2 within the next j
10 ' days outlining the cause of the degradation and plans for restoring
'the structural adequacy of the bolts.
i l g c.
The provisions of Specification 3.0.4 are not applicable.
I L.RVEILLANCE REQUIREMENTS 4.7.11.1 The structural adequacy of the through-wall bolts used to tie rein-forced concrete and steel plate to tne Control Building west and east walls shall be demonstrated at f.he end of:6 months and 1, 3 and 5 years after initial tensioning and at 5-year intervals thereafter. Structural adequacy of the bolts shall be demonstrated by:
Demonstrating that each bolt in a random and representative a.
sample of not less than 25 percent of the total number of bolts has a tension eaual to or greater than 80 percent of the initial bolt tension.
If the tension in any bolt is belcw 80 percent of the initial bolt tension, the tension in two adjacent bolts snall be measured.
If either of these bolts is found to have less than 80 percent of the initial bolt tension, then all bolts shall be tested. All bolts found *a have less than 80 percent of the initial bolt tension shall be reten-stoned to the original installation tension value.
l_
b.
Demonstrating the accectacility of each test sample by showing that 1-2e is greater than 0.8X, where i is the mean tension o
for that sample, e is the standard deviation and X, is the
- This Technical Specification shall become effective upon initial tensioning of the connection bolts.
TROJAN-UNIT 1 3/4'7-37 Amendment No. 47
~ _ _ _ _
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) initial bolt tension.
If this criterion is not met, then all bolts shall be tested to the criteria in (a) above.
If the mean sample tension i is below 0.8X, the circumstances shall o
be reported pursuant to Technical Specification 6.9.1.8.i.
c.
Determining that there is no evidence of degradation or abnor-mal conditions by visual inspection of the ccndition of all bolts in the sample, their end anchorages and concrete or masonry in the vicinity of the anchorage.
In addition, each bolt in the sample will be examined by an in situ ultrasonic test inspection for evidence of cracks or other acnormal degradation.
Abnormal degradation of the bolt shall be reported pursuant to Technical Specification 6.9.1.8.i.
d.
If the bolts inspected during the first four inspections meet the acceptance criteria of (b) and (c), then the samole for the subsequent inspections may be reduced to not less than 10 percent of the total number of bolts.
e.
Beginning with the third year inspection, a trend analysis shall be used to predict the existing bolt tension at the end af the next inspection interval (2 years or 5 years there-
.if ter).
If the precicted bolt tension is below.75 of tne initial bolt tension (i-2: <.75X ), this shall be considered o
as abnormal degradation and reported pursuant to Technical Speci fication 6.9.1.8.i.
f.
A detailed report of any abnormal degradation [as defined in (b), (c) and (e) above] shall be submitted pursuant to Technical Specification 6.9.2 within 90 days af ter completion of the surveillance testing.
4.7.11.2 To assure that the surveillance intervals for the first three g inspecticns in Specification 4.7.11.1 are sufficient to maintain mean bolt tension above.75 of the initial bolt tension, the ' tension in a special sample group of 10 bolts (six in the west wall and four in the east wall) shall be measured at 3-month intervals from initial tensioning. The tension values for the bolts in this special sample group shall be used to determine the pattern of reduction in initial tension with time due to bolt relaxation and shrink / creep of the concrete and greut.
Surveillance of the tension in this special sample group of bolts shall continue until tension reductions have stabilized or until the third year at which time the trend analysis of Specification 4.7.11.1.e shall govern.
If. tension in any bolt in the special sample group ~ falls below.8 of initial bolt tension, the circumstances snall l j be reported pursuant to Specification 6.9.1.8.i.
TROJAN-UNIT 1.
3/4 7-38 Amendment No. 47
PLANT SYSTEMS _
9ASES' CONTP.0L BUILDING MODIFICATION CONMECTION BOLTS b
3/4.7.11 This limitation ensures that the structural adequacy of the modified Centrol Structural adequacy Building will be maintained consistent with the design.
is required to ensure the capability of the Centrol-Auxiliary-Fuel Euilding Ccmplex to withstand safely the Cperating Basis Earthquake and Safe Shut The measurement of tension in and inspection of the througn-ilding at wall bolts ccnnecting the new structural elements to the Centrol Bu Earthcuake.
the specified intervals are sufficient to ensure inat loss of tensien or degradatien of the bolts will not reduce this capability.
i.
The design initial bolt tensien includet a 25 percent allcwance for bolt tension losses due to phenomena such as bolt relaxation, creep of the cen-The com crete and grout and shrinkage of concrete and greut.
su:h phencmena is expected to prcduce a reduction in bolt tensien which is an a; proximately logarithmic function of time, thus the decreasing sample Maintenance of bolt tension above f requency and sample size is appropriate.
.8 of design initial belt tensf en (.8Xo) provides margin abo detect abncr=al degradation of belts which could result in f ailure of bol s
' limit of.75Xo.
The surveillance of the special sample greu-er unexpected Icss of function.
.;ursuant to Specification 4.7.11.2 and the trend analysis pursuant to Speci ificatien 4.7.11.1.e will ensure that 'nean bolt tension will not f al
'.75X between inspections.
c l
l l
i l
i TROJAN-UNIT 1 B 3/4 7-8 Amendment No. 47 1.
i,
k
DESIGN FEATURES DRAINAGE 5.6.2 The spent fuel storage pool is designed and shil be maintained with siphon breakers in the piping extending into the pool which pre-vent inadvertent draining of the pool below elevation 83'11".
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 651 fuel assemblies.
5.7 SEISMIC CLASSIFICATION 5.7.1 Those_ structures, systems and components identified as Category I Items in Section 3.2.1 of the FSAR shall be designed and maintained to the original design provisions contained in Section 3.7 of the FSAR with allowance for normal degradation pursuant to the apolicable Surveillance Requirements except for the Control Building Ccmplex which is subject to Specifications 5.7.2.1 and 5.7.2.2.
- 5. 7. 2.1 The Control-Auxiliary-Fuel Building Ccmplex (Complex) shall be designed and maintained to the design provisions centained in PGE-1020,
" Report on Design Modifications for the Trojan Control Building", as supple-mented by the documentaticn listec in condition 2.C.(12) of the Ocerating License with allowance for nomal degradation pursuant to the applicable Surveillance Requirements.
- S.7.2.2 No modifications which will result in a net:
(a)
I percent increase in la:eral shear forces on any story of the Ccmplex; (b)
I percent decrease in la:eral shear resistance of any story of the Complex; (c) 5 percent increase in combined interstructure displacements between the Centrol and Turbine Buildings; or (d) 5 percent reduction in clear space between the Turbine and Control Buildings shall be performed without prior approval of the Director of Nuclear Reactor Regulation.
The modifications to the Control Building approved in License Condition 2.C.(12) are not subject to the above limitations.
An increase in equipment weight not to exceed 10 percent on a per story, per building basis is permissible and excluded from consideration under this specification.
- Effective upon completion of the Control Building modification program TROJAN-UNIT 1 5-6 Amendment No. /g, //, 47 i
DESIGN FEATURES 5.8 METEOROLOGICAL TOWER LOCATION 5.8.1 The meteorological tcwers shall be located as shown on Figure 5.1-1.
l 5.9 COMPONENT CYCLIC OR TRANSIENT LIMIT f
5.9.1 The components identified in Table 5.9-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.9-1.
4 4
e e
I 1
)
a 4
s I
e
-.