ML20058A242
| ML20058A242 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/09/1978 |
| From: | Short T OMAHA PUBLIC POWER DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7811170193 | |
| Download: ML20058A242 (83) | |
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Olnaha Public Power District 1023 HARNCY a OMANA, NC8HASKA 68102 e TELEPHONE 530 4000 AHPA CODE 402
!iovember 9, 1978 Director of : uclear Reactor Regulation ATT!!:
Mr. Robert W.
Reid, Chier g
Ope rat int-Reactors Branch :!c. h d
U. C. :Iuclear Regulatory Comission s"
Washinc; ten, D. C.
20555 r
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References:
(1) Decket I!c. 50-285 (2) Applientien for_A:: en ent of Facility Operatinc Licence, Dated Septeuber 9, 1977, Relating to Plant Operating Modes :lecessarj-for the Perfomance of Surveillance Tects Cen tler.en :
!' embers of your staff have requested additional justification re-garding the referenced request for amendnent of cur Facility Operating License.
Enclosed nre forty (LO) ecpies of the requestel justificaticn.
Also, because several trendments to our Facility Cperating License have been issued since the above-referenced a.enitent was filed with the Cc=i c c i on, forty (!.0) ecpies of a complete set of preposed Technical Specificaticu reflectin; past esendments are being provided for your reference in prccencing our application.
The District emphasinen that the sub,!ect application does not seek any chsnces to the surveillaace tests, frequencies for perforning tests, or, in cay otner way, reduce the level of surveillance asacciated with the respective testing.
It merely specifies the r? quired crersting ncdes in ceder to perfern these tests to insur' ccupenent operability d'tring the time when the Liniting Ccnditions for Cperation are appli-cable.
Sincerely,
\\o 1..r l 9
.f ( &
o a T. E. Short Divisica Manager Production Operations TEG/CM/3JH :Jmn Enclosures O(
cc: Le3ccur, Lamb Leiby & MacBae M11170(G i
o 1757 " !" Otreet, :l. W.
T Washincton, D. C.
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DISCUSSI0'!
Page 1 of the " Definitions" secticn of the Technical Specifications is revised to incorporate a definition for " Operating Modes", as requested and as contained in our application dated January - 27,1970. The remainder of Page 1 of the " Definitions" section remains unchanged.
The following justificulons apply to Table 3-1 of the referenced application:
Iten 1.a.
This check is to be performed during the power operating mode only, since a comparison of the power output indication from the power range safety channels can enly be made during power cperation. Performance of this chech during other operating modes provides no meaningful information.
Item 1.b.
Adjustments to the power range safety channels can only be made during the power operation mode, with the power level above 205 of rated power, since heat balance calculations below this value are inaccurate. Adj ust-ments made while the plant is in other operating modes vould result. in erroneous output indication from the power range safety channels.
I te n 1. c.
The calibration and testing of the power range channels using the internal test cignal to verif" trips, alams, etc. cannot be performed when the plant is in a cold shutdown or refueling eendition because the power range safety channels are outside of their norral operatin ; range-
. In additica, the calibration and testing while the plant is in a cold shutdevn er refueling mode does not provide any meaningful or useful in-formation.
Item 2.a.
This check vill be performed every shift in all cperating mc des.
Iten 2.b.
This test will be performed prior to each startup while the plant is in a cold shutdown ecnditicn only, since the performance of this test in other operating modes is impossible and would not provide meaningful in fomaticn. The specification vill be satisfied by performing the test in this operating node.
1
1
,o y
Item 3. a.
This check cannot be performed while the ' plant is in a cold shutdown or refueling node, cince the reactor coolant pumps are normally not in service and, therefore, flow signals are not available.
Iten 3.b.
This calibration cannot be performed while the plant is in power operation or hot standby, since access to the sensors is not possible or decirable due to high radiation levels.
Performcace of this test at each 18 month interval, while in the cesignated operating mode, vill pro-vide adequate calibratica of these loop devices and vill satisfy the speci fic at icn.
Item 1.c.
This test vill not be perf
.ed while in the cold shutdown or re-l fueling modes becauce the test vould not provide any meaningful inforn-i aticn and reactor coolant flow circuitr/ need not be operable daring these moder, of operation.
Item h.a.
These cl.ecks vould not be performed when the plant is in a ccid shut-down or refueling mode, civace the rence of temperature indication is nct sufficient to perform testinc at less than 5150F.
Item h.b.
The calibration vculd be performed at each 18 month interval while the plant la in hot shutdown, cold shutdown, or refueling modes. Per-i formance of these calibrations requires acceca to the pressure and tem-perature sensors and, therefore, is not performed when the plant is in power operation or het ctandby due to inaccessibility of thece sensors.
The requirement of the Technical Specifications can be fulfilled by per-forming these calibratient during the specified modes of operatien.
Item L.c.
These ' testa vould not to performed when the plant is in the cold chutdevn or refueling modec, since no meaningful information could be obtained and operability of the TM/LP circuitry is not required in the cold shutdown or refueling modes.
Iten 5.a.
These checks vould not be performed when the plant is in the cold shutdown or refueling modes, cince these pressure indicators 'are not utilized durin6 Jov or reduced prescure operation.
2
s.
Item 5.b.
These calibraticns would not be performed when the plant is in the power operation, hot shutdown, or hot standby conditions, since access to the sensors is restricted because of radiological considerations. The l
perron ance of the test during each 18 nonth interval, while in the cold shut-down or refueling ccdes, will satisfy the requirement of this specification.
Iten 5.c.
These testa vould not be performed while the plant is in a cold shutdown er refueling condition, since no neaningful information could be obtained and the high pressuricer pressure circuitry is not required in these codes of operation.
Item 6.n.
'"hese checks vill not te performed when the plant is in a cold-shutdem condition because the sieam generator levels may be in a tran-sitica state and no meaningful data vould be obtained.
In addition, the operability of the ste1= cenerator level circuitry is not required in this cperating mode.
Item 6.b.
These calibraticns would te done at each 18 =cnth interval, regard-less of the cperating mode of the plant.
Item 6. c.
These tests veuld not be perferred while the plant is in a cold shutdevn er refueling ecnditien, since no neaningful infcrmation could be cbtained and the operability of these circuits is not required in there operating medes.
Item 7.s.
These checks vould net be performed while the plant is in a refuel-ing =cde, since no pressure indicaticns are available.
Iten *
.2.
These calibraticns would be perforned at each refueling, reg 1rdless of the operating r.cde of the plant.
Iten 7.c.
These tests would not be perforced while the plant is in a cold shutdown or refueling mode, since no meaningful information could be obtained and the operability of the steam generator circuitry is not re-quired in these operating medes.
3
Item 8.a.
l These calibrations vould be performed at each 18 month interval, regardless of the operating mode of the plant.
I_ty, 8.b.
t I
j These testa vould not be perfomed while the plant is in a refuel-I ing mode, cince the operability of these preccure switches is not re-quired when there is no possibility of the need for the operation of thic switch during this mode of operation.
Item 9.a.
Thic test would be perfomed at a cpecified interval while the plant in in a het shutdown ecnditicn cnly, since the perfomance of this test, while the plant is in the power cperating or hot standby modes, vill re-sult in a turbine trip and, while the plant is in a cold shutdown or re.
fueling mode, the turbine main steam stop valves are not open.
Item 10.a.
This test vould be perfcrmed at a specified interval while the plant is in a hot shutdown conditicn enly, since the performance of this test, while the plant is in the power cperating or hot standby modes, vill re-sult in a turbine trip and, while the plant is in a co3 d shutdown or re-fueling mode, the turbine main steam stcp valvec are not open.
Iten 11.a.
In order to perfom this test, the CD'4 clutches nuct be energiced.
These clutches may not te energiced in operating modes other than power cperntien and hot standby.
Iten 12.a.
These checkc would be performed during a power operating mode only, since adequate pcver signals are not available for the nececsary ecmpari-cens until the plant is at a p0ver level greater than 155.
Iten 12.b.
These calibrations vill be perforned regardless of the operating node cf the plant.
Item 12.e.
These tests vould not be performed while the plant is in the cold shutdcun er r Neling conditions, since these circuits are out of ser-vice or incperable during these modes.
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e The following justifications apply to Table 3-2 of the referenced application:
Item 1.a.
These checks vould not be performed during the cold shutdown or re-fueling modes, since these pressure indicators are not utilised during re-duced pressure operation.
Iten 1.b.
These calibrations would be performed at each 18 month interval i
vhile the plant is In a cold shutdevn or refueling mode and would saticfy this Technical Specification.
Item 1.c.
There tests vould not be performed while the plant is in a cold shutdown or refueling mode, since the tests would not provide any mean-ingful informatien, and these instrument channels are inoperable during these medes.
Item 2.a.
These calibratiens are part of the calibrations listed in Item 1.b.
end, therefore, the sane justificaticn applies.
Item 3.a.
These tests are performed to dencnstrate operability of che saf ety injectica actuation circuits which t.re not required during cold shutdown or refueling ecnditions and, therefore, the performance of these tests when tl:e plant is in these operatirc modes prevides no useful information and, additienally, these circuits may be inoperable during the cold shut-down or refueling medes.
Item L L.
This test is performed cnly while the plant is in a refueling mode, since the reactor ecolant system must be in the refueling mode before the test can be performed, i.e., reactor /essel head removed. Performing the test in the specified cperating mode vill satisfy thic specificatien.
Item L.a.
The calibration of this circuit while the plant is in the cold shut-down or refueling modes vill satisfy this specification.
Item h.b.
This test vill not be performed while the plant is in the refueling mode, since the containment pressure high signal is not necessary to in-sure plant safety when the plant is in the refueling mode.
5
4 Item 5.a.
These tests vill not be performed while the plant is in a cold shut-down or refueling mode, since the operability of this circuit is not re-quired when the plant is in these operating modes.
Item 5.h.
The performance of this test at 18 month intervals, while the plant is in the cold shutdown or refueling moden, vill satisfy this specifica-tien.
Item 6.a.
7nese checks vill be performed recardless of the plant operating mode.
Ite., 6. b.
These tests vill be perfermed regardless of the plant operating mode.
Itam 6. e.
These testa vill te performed regardless of the plant operating mode.
Item 7.a.
The performance of this test at 18 month intervals while the plant is in a refuelin6 00ndition will catisfy this Technical Specification.
Item 8.a.
The perfornuce of this test at 18 month intervals while the plant is in a refuelin,; condition vill satisfy this Technical Specification.
Iten S.b.
The perfor::ence of this test at 18 mcnth intervals while the plant is in a refueling cendition vill satisfy this Technical Specification.
Iten 9.a.
The performance of this test at 18 month intervals while the plant is in a refueling cendition vill satisfy this Technical Specification.
Item 10.a.
This test is performed in conjuncticn with Item 3.a. and, therefore,
the sane justification applies.
Item 11.n.
These tests are not perfornd when the plant is in a refueling mode, since the diesels are not required when the plant is in this operating mode, and it is during these periods of time when the diesels are over-hauled and, therefore, not available for testing.
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1 Iten 11.b.
This test is performed in conjunction with Item 3.a. and, therefore, the same justification applies.
Iten 11.c.
This test is performed in conjunction with Item 3.b. and, therefore, i
the same justification applies.
l Iten 11.d.
l This test is performed prior to taking the reactor critical, if not completed in the previous week, and therefore the operating modes apply to those mades when the plant is not critical, i.e., hot shutdown, cold shutdown and refueling.
Item 12.a.
These requirer.ents are the same as for Item 11.a. and, therefore, the same justification applies.
Item 13.a.
These checks are performed when the SIRW tank level is such that level indicatien is provided.
- ' hen the plant is in the cold shutdown n
or refueling modes, the SIRW tank may not have adequste level, since the contents of the tank during the cold shutdown and refueling modes may have been pumped into the reactor venrel.
Iten 11.b.
Thece checks are performed when the SIf.4 tank level is such that level indicaticn is provided. When the plant is in the cold shutdown or refueling modes, the SIEW tank may not have adequate level, since the centents of the tank during the cold shutdown and refueling modes may have been pumped into the reacter vessel.
Iten 11.c.
These calibrations are performed regardless of the operating mode of the plant.
Iten IL.a.
These checks are not performed while the plant is in a cold shut-down or refueling mode, since the safety injectica tanks may be empty and depressurised while the plant is in these modes, it;Sm IL.b.
These calibrations vill be performed regardless of the operating mode of the plant.
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Iton 15.a.
These checks are not performed while the plant is in cold shutdown or refueling nodes, since maintaining boric acid tank levels during these operating modes is not required and the tank (s) may be out of service for maintenance purposes.
I Iten 15.b.
i The performance of these tests at 18 nonth intervals while the plant is in the cold shutdown or refueling modes vill satisfy this specifica-
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I tion.
Item 15.c.
These calibratiens vill be performed regardless of the rperating i
node of the plant.
i Item 16.a.
These checks vill be perferned regardless of the operating mode of the plant.
Item 17.a.
j These checks vill not te performed while the plant is in the cold
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shutdown or refueling nodes, since pressure indicaticns are not avail-
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able, as they are out of service.
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f Iten 17.b.
These tests are not performed while the plant is in the cold shut-(
devn or refueling modes, since the steam generater 1cv pressure signals are nct required unless the steam generator pressure is above 550 psia.
7 Iten 17.c.
These tests are not performed while the plant is in a power opera-tion, hot standby or hot shutdsvn cenditien, since the sensor's accessi-bility is restricted when the plant is in these cperating modes. The calibration at 16 conth intervals vill insure operability of these chan-
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nels and vill satisfy this specification.
Item 18.a.
This check is not perfonced while the plant is in a cold shutdown or refueling mode, since the contents cf the SIRW tank may be trans-ferred to the reactor coolant system during these modes of operation.
I Item 18.b.
This check is not perforned while the plant is in a cold shutdown or refueling mode, since the contents of the SIR'J tank may be trans-L ferred to the reactor coolant system during these. codes of operation.
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l Item 19.a.
This test is not performed unless the plant is in a refueling mode, since this mode is necessary to perform this test. Performing this test while in the specified rode vill satisfy this specification.
Item 20.a.
j This test is perforr.ed as part of Item 3.a. and, therefore, the same justificaticn applies.
Item 20.b.
This test is not performed unless the plant is in a refueling modo, since this node is necessary to perform this test.
Performing the test while in the specified mode vill satisfy this specification.
The foileving justificaticns apply to Table 3-3 of the referenced applicaticn:
Item 1.a.
These checks are not performed while the plant is in a cold shut-down or refuelin6 mode, since CEA's are inserted while the plant is in these modes.
Item 1.b.
These checks are not performed while the plant is in a cold shut-down or : efueling mode, since CEA's are inserted while the plant is in these modes.
Item 1.c.
These calitrations are performed only when the plant is in the re-fueling shutiovn mode, since this mode is required in order to perform thece calibraticns and performin6 these calibrations while in the speci-
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fied mcde vill satisfy the specification.
Iten 2.a.
These checks are not performed while the plant is in a cold shut-down er refueling mcde, since CM's are inserted while the plant is in this mode.
Item 3.b.
This test is only performed while the plant is in power operating modes beer.use all CEA's must be withdrawn in order to perform this test and, therefore, it is not possible to perform the test in other operat-ing modes.
9
Item 2.c.
These tests are perforned at normal temperature (-5320F) and pressure
(-2}00 paia) at each 18 month interval while the plant is in a hot shutdown ccnditicn and satisfy this specification.
Item 3.a.
These checks vill be perforced regardless of the operating mode of the plant.
Item 3.b.
These checks will be perforned regardless of the operating node of the plrint.
Item 7.e.
Thast checks vill be performed regardless of the operating node of the plant.
Item h.a.
These checks will be performed regardless of the operating mode of 1
the plant.
Item h.b.
These checks vill be performed regardless of the operating mode of the plant.
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Item 5.a.
These checks vill be performed regardless of the operating node of 4
the plant.
Item 5.b.
These checks will be performed regardless of the operating node of the plant.
Iten 6.a.
These tests cre not performed while the plant is in the cold shut-down or refueling nodes, since pressurizer level signals are not avail-able during these modes of operation.
Item 6.b.
This calibration vill be performed regardless of the operating mode of the plant.
Iten 6.e.
This test is not perforned while the plant is in the cold shutdown or refueling modes, since pressurizer level signals are required in order to perform this test and does not provide meaningful information while the plant is in a cold shutdown or refueling mode.
Item 7.a.
Thi= test is only performed while the plant is in a cold shutdown
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i Iten 7.rs.
(Continued) r j
condition because extensive CEA motion is required and, therefore, can only be done while the plant ic in this cperating mode
~5320F/-2100 pala.
Performing this tect while in the cpecified mode vzil natisfy the specification.
Item 8.a.
Thin test 13 performed only when the plant is in the power operation, l
hot standby, or hot chutdovn condition, cince thece ccnditions must be i
established in order to perform this test. The requirement to perform thic test at 18 month intervals will be catisfied.
Item 8.b.
t This tect is performed only when the plant is in the hot chutdown condition, cince hic condition must be establiched in order to perform i
a t
i thic test.
The requirement to perfona this tent at 18 month intervals t
vill ta caticried.
Iten 9.a.
This calibraticn vill not be performed while the plant is in the power operating mode, since the performance of this calibration requires f
an interruption in the feedvater flow signals and, therefore, cannot be f
perf orned while the plant is in the operating mode. The requirement to j
perform thic test et 18 month intervals vill be saticried.
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Item 10.a.
- i This test vill te performed regardless of the operating mode of the plant.
Item 10.b.
l This test vill be performed regardless of the operating mode of the I
plant.
I Item 11.a.
This tect will not be performed while the plant is in power cpera-tion or hot standby conditions, since containment access is required.
This test vill be performed at the cpecified 18 month interval while the plant is in the specified operating medes.
e Item 12.n.
i This tect will be performed at the 18 month interval while the plant is in cold shutdevn or refueling modes, which is a required made in order l
to perform this tect.
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,,, - - -. -, - - --., -, -,, ~,,,.,
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l Item 13.o.
l This test vill be perfcrmed regardlecc of the operating node of the I
p] ant.
1 Item 14.a.
I This test vill be performed regardless of the operating mode of the plant. Also, the surveillance method for this tect has been clarified and now stipulates a requirement for conparinc annulus temperature read-f
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ings which provide a more specific definition of what is being tested.
4 Item IL.b.
I' j
This test vill not be performed while the plant is in a power operating i
mode cr hot standby mode, since accecc to the RTD's and the reactor cavity is restricted durin.; there operating nodes. The requirement to perform j
thin test at 18 month intervals vill bc =atisfied. Also, the surveillance
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l method has been nore clearly defined for thic calibration.
k Item 15.a.
l This check vill not be performed while the reactor is in a cold t
shutdown or refueling mode, cince normally the reactor coolant pumps are l
chutdown during these operating modes and, therefore, reactor coolant flow rate indication is not available.
Itea 16.a.
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1 1
This check is not performed while the reactor is in a cold shutdown r
j or refueling mode, since pressurizer pressure signals are required to l
make the specified ecmparison.
Iten 17.a.
This check is performed only when the plant is at power and above 15% of rated power, since no meaningful or reliable data can be obtained f
at other conditions.
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Item IS.n.
t This test will not be performed while the plant is in a refueling mode, since the operability of these valves is not required while the plant is in that mode of operation.
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4 Item 18.b.
These calibrations vill be performed only when the plant is in a j
refueling mode, since cycling of the valves is required in order to per-fona this test. The requirement to perform this test at 18 month inter-l vals vill Le satisfied.
The following justifications apply to Table 3 h of the referenced application:
I Items 1.(s), 1. (b), nnd 1. f e )
5 The required operating modes for the performance of Items 1. (a),
- 1. (b), and 1. (c) are already given and the " Operating Mode Required for Testinc" eclumn is added merely to be consistent with the format of the renainder of this application.
4 Iter 2.
1 P
This test vill be performed regardless of the operating mode of the plant.
Iten 3.
This test vill be performed regardless of the operating mode of the L
plant.
l Item L.
3 This test vill not be performed while the plant is in a cold shut-dcvn or refueling mode, since SI tanks are not required while in these operating modes and the tanks may be empty.
Iten 5.
These tests vill be performed regardless of the operating mode of the plant.
l Item 6.
These tests vill not be performed while the plcat is in a cold shut-down or refueling mode, Jince no meaningful data could be obtained by performing this test.
Item 7.
These tests will be performed regardless of the operating mode of f
I the plant.
Item 8.
1 These tests vill be performed regardless of the operating mcdc of the plant.
Item o.
i These tests vill be performed regardless of the operating mode of f
t the plant.
13
The following justifications apply to Tabic 3-5 of the referenced application:
Item 1.
This tect vill only be performed while the plant in in the hot chut-i down condition becauce the performance of this test is impossible either because the CEA'c are fully inserted (Modec h and 5) or would result in severe flux distortion (Modec 1 and 2).
Item 2.
These testc vill be performed only while the plant is in the power operation or hot standby modes, since it is only during thoce modes that CEA's must be demenctrated cperable and also because the CEA's are fully incerted in the other cperating modes.
1 Item 3.
This test vill te performed at each refuelinc outace while the plant is either in the cold chutacvn or refueling modes when the plant is de-pressuriced. This tect require the operation of these safety valves and can most safely te done only when the plant is in these modes.
Iten L.
These tests require the operaticn of thece valves and are perfonaed while the plant in between the hot shutdown and the cold shutdown condi-tienc. Since these tests are only required at each refuelinC, the per-formance of thece testa at these modes satisfies the requirement.
1 Item 5 Thic tect vill be performed regardlecc of the operating mode of the plant.
Item 6.
This tect vill be performed only while the plant is in the cold shut-down or rc. 2eling modes, since in order to perform this test the lov vater supply to equipment muct te interrupted.
Since thic test is only required at each refueling cutage, the performance of these tects during these operating modes saticfies the tectinc requirement.
Item 7.
This test vill be performed regardless of the operating mode of the plant.
Item 8.
This test vill not be performed during cold chutdown or refueling 9
1 1h
i Item 8. (Continued) modes, since no meaningful data could be obtained and reactor coolant system leakage is not a meaningful parameter when the plant is in these operating modes.
Item 9 This test vill not be perfonaed when the plant is in a refueling mode, sinca the diesel generator availability is not required with the plant in this operating mode.
Item 10.
These testa vill be perforned regardless of the plant operating mode.
Item 11.1 and 11.2 This test will be performed while the plant is in the cold shutdown or refueling modes, since access to the equipment is restricted during other modes of operation.
The required testing while the plant is in the specified operating medes vill satisfy this specification.
Item 12.
Fuel incpections are performed cnly during cold shutdowns or refuel-ing outages.
Item 13 This calibration vill be performed only when the plant is in the cold shutdevn or refueling modes. The requirement to calibrate these devices once each refueling vill be satisfied by performing these cali-brations while the plant is in these operating ncdes.
The following justifications apply to Section 3.4 of the referenced application:
Iten 3.h(1)
Change is requested in order to make this specification consistent with specification 2.1.2.
Item 3.h(2)
Since the referenced modificaticns can caly be made while the plant is in a cold shutdevn or refueling mode, the appropriate operating modes are referenced in this specification.
Item 3.k(3)
Since the referenced modifications can only be made while the plant is in a cold shutdown or refueling =cde, the appropriate operating modes are referenced in this specification.
15
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t e
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The fviloving justifications apply to Section 3.5 of the referenced application:
Iten 3 5(1)
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This chance specifies that the Type A test will be performed while the plant is in a refueling mode, which is the specified node for the performance of this test.
Iten 3. 5(2)a. fif t )
I These tests vill be performed regardless of the operating r. ode of the plant.
t Iten 1.5(2)c.
I This chance specifies that the personnel access hatch test is not I
I required unlens ccntainment integrity is required. The existing speci-ficationc can be interpreted to require this tect, even though the per-f cor.nel accesc hatch may remain open.
The requented change alco specifies l
1 that the testing for mechanical and electrical penetrationc will be per-
[
forced regardleca of the operating ncde of the plant and alco specifiec l
l that the equipnent hatch and the trancrer tube vill only be tested when the plant ic in a cold chutdown or refueling node.
The performance of f
r the testing on equipment hatch and transfer tube during cold shutdevn l,
or refueling intervals vill sati:fy the requirements that these tests be performed during each reactor shutdown for a najor refueling, but in no cace at intervalc greater than two years.
l t
j Iten 1.5(3)c.
I j
These testa vill be performed while the plant is in a cold shutdown I
r or refueling node. The performance of these tests while in these operat-ing ccdes will fulfill the requiremeht that these tests be performed during
)
each reactor chutdcyn for major refueling, but in no case at intervalc l
1 grcater than two years.
t Item 3 5(5)a.
These inspecticna vill be performed only when the plant is in a hot l
5 standby, cold shutdown or refueling made, in order to fulfill the re-i quirement that the test be performed at each reactor shutdown for a re-J i
fueling outage and prior to any Type A tect.
[
Item 3 5(6)a.
i No cpecific operating mode is specified, other than specifying the i
reactor coolant ccnditicn which must exist in order to perform these testo.
i i
16 I
---.~.::--
i Iten 3 5(7)d.
These tests will be performed regardless of the operating mode of i
the plant.
t The following justificaticna apply to Section 3.6 of the referenced f
)
application:
L Iten 3.6(1)
This change specifies that the test vill be performed while the plant
?
is in the refueling mode only because this operating mode must be established i
j I
in order to perform this test, i.e., reactor vessel head removed.
I Item 3.6/2)n.
j This chance cpecifies that the test vill be performed only when tha plant is in the refueling mode. The requirement to perform thic test f
t' at each reactor refueling interval vill be satisfied by performing the i
test while the reactor is in the refueling mode.
1 Iten 3.6(2'b.
l Tnese tects vill be performed coly when the plant is in a cold shut-
[
i down or refueling mode, since during other modes of operation accecc to i
thu spray no::les is restricted. The testing requirement of the speci-f r
ficaticn vill be satisfied by performing the test while in the cpecified i
operating mcdes.
i Item 3.6(2)d. (ii) t This test vill be performed regardless of the operating mode of the plant.
I Iten 3.6(3) l i
j Pump testing is not required fcr the cold shutdevn or refueling operat-ing modes for the following reasons:
1.
The emergency core ecoling s/ stem is not required to be cperable.
t I
2.
The shutdcwn cooling pumps are in ecntinuous operation during t
these operating modes.
i t
3.
Full flew tecting is performed during the refueling operating mode, sa indicated in Item 3 7(1)c.
i Iten 3.6(hh._
t i
Pump and valve testing is not required for the cold shutdown or re-i i
fueling operating modes for the following reascns:
1.
The emergency core cooling system is not required to be operable.
[
2.
The shutdown cooling pu=ps are in continuous operation during these cperating medes, j
17 I
.m
- =
- ~.
r I
i t
Item 3.6(h) (Continued) i
~
3.
Full flow testing is perforned during the refueling operating
[
mode, as indicated in Item 3 7(1)c.
Item 3.6(L)b.
This test vill be performed during het shutdown mode at 18 month intervals.
Item 3.6(5)a.
The testing described in this item can only be performed durf ng the cold shutdown or refueling modes, when these systens are not required for operation.
Item 3.6(5)b.
This test vill be performed regardless of the operating mode of the
- plant, a
Item 3.6(5)c.
This test vill be performed regardless of the operating mode of the plant.
Item 3.6(5)d.
I Containment access is required to perforn the described testing; therefore, these tests are conducted at cold shutdevn or refueling modes of cperation. The specification vill te satisfied by performing the tests while the plant is in the specified cperating medes.
Item 3. 6( 5)e.
Centainment access is required to perform the described testing; therefore, these tests are conducted at cold shutdevn or refueling modes 1
of operatien. The specification vill be satisfied by performing the tests while the plant is in the specified cperating modes.
Item 3. 6( 5 )f.
l These tests vill be performed during the hot shutdevn, cold shut-down or refueling modes of cperaticn, when centainment access is avail-able in an effort to reduce persennel exposure. The specification vill be satisfied by performing the tests while the plant is in the specified operating modes.
Iten 3. 6(5)c.
This test will be performed regardless of the cperating mode of the plant.
[
I 18
t j
The following justifications apply to Section 3 7 of the referenced application :
Iten 1.7(1 )a.
These tests vill not be performed during the refueling node of opera-tion as the diesel generators are not required to be operable.
Iten 3.7(1)b.
These tests will not be performed during the refueling mode of opera-tien as the diesel generators are not required to be operable.
Item 3.7(1)c.
These tests can only be performed during the refueling mode of opera-tion, when the reactor head has been removed in order to provide full flow safety injection to the core.
Iten 3 7fl)d.
These tests vill be performed regardless of the operating mode of the plant.
Iten 3 7(1)f.
These tests vill nct be performed during the refueling mode of opera-tion, since the diesel generators are not required to be operable during this mode.
Item 3.7(2)a.
This test vill be performed regardless of the operating mode of the plant.
Item 3.7(2)b.
This test will be performed regardless of the cperating mode of the a
plan t.
Item 3.7(2)c.
This change specifies that the test vill be performed only when the plant is in the refueling node. The requirement to perform this test at each reactor refueling interval vill be satisfied by performing the test while the reactor is in the refueling mode.
Iten 1.7(2)d.
This test vill be performed regardless of the operating mode of the plant.
Item 3.7(2)e.
l This chcnge specifies that the test vill be performed caly when the plant is in the refueling mode. The requirement to perform this test at each reactor refueling interval vill be satisfied by performing the test while the reactor is in the refueling mode.
19
i Item 3 7(1)n.
This chance specifies that the test will be performed during the cold shutdown or refueling modes of operation. These modes of operation 4
satisfy the refueling shutdown frequency specified.
1 Item 3. 7( 3)b.
Thia test will be performed regardless of the operating mode of the j
pl ant.
Iten 3.7(h)
This test cannot he performed at reactor coolant system temperatures greater than 3000 because normal electrical systems must be operable.
i The folleving justification applies to Section 3.8 of the referenced j
applic aticn :
Item 3.8 l
t Cold shutdown or refueling modes of operation are required as these 2
are the only ccnditi:ns when there is no nain steam flov. These modes e
i of operatien satisfy the refueling shutd:im frequency specified.
i The following justificatien applies to Section 3.9 of the referenced applicatien*
t i
Item 3.0 j
The testing cannot be performed during cold shutdevn or refueling modes of operation because the steam generators are not at normal cperat-inc pressures.
The fc11cving justification applies to Secticn 3.10 of the referencei application:
Item 3.10(1)a.1.
1 The operating modes are specified in accordance with the requirements I
of this specification, i
Iten 3.10(1)a.2.
f The operating modes are specified in accordance with the requirements I
of this specification.
[
Item 3.10(1)b.
The operating modes are specified to be consistent with the operating nodes which the plant must be in in order to perfcrm this test.
[
Item 3 10(2) throuch Item 3.10(7) l l
The operating modes are specified and are those modes which the plant t
l must be in in order to perfonn these tests.
20 i
The following justifications apply to GeJtion 3.11 of the referenced appliention:
Iten 3.11(1)
These testa vill be performed regardless of the operating node of the plant.
Item 3.11(2)
These tente vill be performed regardlees of the operating node of the plant.
The following justifications apply to Section 3.12 of the referenced application:
Item 3.12(1)
These tests will be performed regardless of the operating node of the plant.
Item ?.12(2)1.
These tests vill be performed regardless of the operating rode of the plant.
Item 3.12(2)c.
These tents vill be performed regardless of the operating mode of the plant.
Item 3 12(2)d.
These tests will be performed regardless of the operatinc mode of the plant.
Item 1.12(2 }e.
The testing in this item requires the power operation and, therefore, catisfies this specification.
Item 1.12(2)f.
Testing during the cold shutdovn or refueling modes of operation is not required, since there is no steam generatcr bicvdown in operation.
The folleving juctificatiens apply to Table 3-11 of the referenced application:
Item A.
This test will be performed regardless of the operating mcde of the plant.
Item B.
These tests cannet be perft med during the cold shutdovn or refuel-ing modes of operatien, since the blovdcun system is not in cperaticn.
21
The following justifications apply to Table 3-12 of the referenced application:
Iten A.
These tests vill be performed regardless of the operating mode of the plant.
Item B.
These tests vill be performed regardless of the operating mode of the plant.
L Item C.
These tests cannot be performed during the cold shutdown or refuel-
)
ing modes of operation, since the cendenser is not in operatien.
Iten D.
These tests vill be perforned regardic ss of the operating mode of j
the plant.
The following justification applies to Geetien 3.13 of the referenced application :
Item 1.13 These tests will be performed regardless of the operating mode of the plant.
The follevin6 justifications apply to Section 3.15 of the referenced applicatien. This section was issued as Amendment No. LO to our specifi-cations and was not included in the above-referenced request for amend-4 ment because Amendment No. LO was issued later.
Item 3.15(lla.
These tests vill be performed regardless of the operating mede of the plant.
Iten 3.15(lit.
Operating modes are specified censistent with the. specificC-ion.
Iters 7.15(2)a.,
b.,
c.. d.1, d.3, e.,
f., 3.15(3). (LI. (5),'(6)a.
(6)b..
and i'f)
These tests vill be performed regardless of the operating mode of the plant.
Item 3.15(2)d.2 Technical Specification applies only to non-testable ecmponents during power operatien.
Item 3 15(6)c.
Operating mcde designation consistent with requirement of Technical Specificatien.
I 1
4
j The following justification applies to Section 2.2 of Appendix B of the referenced application:
Item P.2 1.
These tests will be performed regardlecs of the operating mode of the plant, when the circulating water punp(s) are in operation.
i f
'l I
4 1
I h
b 9
6 l
23
n I
TECIUlICAL SPECIFICATIOIS DEFI!!ITIO:!S The following terns are defined for uniform interpretaticn of these Speci-fications.
REACTOR OPERATI!!G CO:iDITIO!IS Rated Power A steady state reactor core output of 11420 R4t.
Reactor Critical The reactor is considered critical for purposes of adninistrative centrol when the neutron flux logarithmic range channel instrumentation indicates greater than 10 I'". of rated power.
Oneratinc !! odes - As specified by the following definitions, as used in surveillance requirenents of these Specifications, means that surveillcnce is required to.te performed at specified frequencies only if reactor is in specified operating mode, with the following excepticn:
4 Surveillance scheduled for 18 month intervals (+25%) vill be performed even if reactor node of cperation must be changed to specified mode of operation.
Pover coeration Conditien (Operating !! ode 1)
The reactor is in the power operation ecndition when it is critical and the neutron flux power range instrumentaticn indicates greater than 2%
of rated power.
Hot Standhv Conditien (Operating Mode 2)
The reactor is considered to be in a hot standby condition if the average temperature of the reactor ecolant (Tavg) is greater than 515 F, the re-l C
actor ic critical, and the neutron flux power range instrumentation in-dicates less than 2% of rated power.
Hot Shutdown Conditien (Operating Mode 3)
The reacter is in a hot shutdown ecndition.if the average temperature of the reactor coolant (Tavg) is greater than 515CF and the reactor is sub-critical by at least the amount defined in Paragraph 2.10.2.
Amend::.ent flo. 32 1
i e
TABLE 3-1 IfIND!UM FREQUE'ICIES FOR CHECKS. CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTE4 1
Operating Mode
- Surveillance Required Channel Description Function Frequency For Testing Surveillance ??ethod 1.
Power Range Safety a.
Check S
1 a.
Co parison of four power Channels channel readings, for both neutron flux and thermal power.
b.
Adjustment D
1 b.
Channel adjustment to agree
(>20% pvr) with heat balance calculation.
(+1%)
I}
1, 2 or 3 c.
Internal test signal to veriCr c.
Calibrate M
and Test trips, alarms, turbine runback signal, permissives and auc-tioneer circuits, id w
2.
Wide-Range Logarithmic a.
Check S
1, 2, 3, 4 or 5 a.
Comparison of four vide-range Neutron Monitors readings.
IW)
P 3
b.
Internal test signals to veriRy b.
Test SUR indication and trip, power level permissives, instrument accuracy.
3 Reactor coolant Flow a.
Check S
1, 2 or 3 a.
Comparison of four separate total flow indications, b.
Calibrate R
3, 4 or 5 b.
Known differential pressure applied to sensors to cali-brate all loop devices.
Bistable trip tester.IUI IY) 1, 2 or 3 c.
c.
Test M
" Operating Mode Required For Testing suggests the operating mode necessary to perform the surveillance test in order to obtain meaningful results and/or data, t
~l TABLE 3-1 (continued)
MINIMUI4 FREQUENCIES FOR CHECKS CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTD4 h.
Thermal Margin /Lov a.
Check:
S 1, 2 or 3 a.
Check:
Pressure
- 1) Temperature
- 1) Comparison of four separate Input calculated trip pressure set point indicetions.
- 2) Pressure
- 2) Comparison of four pres-Input surizer pressure indi-cations (same as 5(a) below).
b.
Calibrate:
R 3, 4 or 5 b.
Calibrate:
- 1) Temperature
- 1) Knewn resistance substi-Input tuted for RTD coincident with known pressure input.
- 2) Pressure
- 2) Known pressure applied Input to sensor coincident with above temperature cali-brations.
Bistable trip tester.(U) c.
Test M(V) 1, 2 or 3 c.
5 High-Pressurizer a.
Check S
1, 2 or 3 a.
Comparison or four separate Pressure pressure indications.
b.
Calibrate R
h or 5 b.
Known pressure applied to sensors.
Bistable trip tester.(U) c.
Test M(V) 1, 2 or 3 c.
~
TABLE 3-1 (continued)
MINIMUM FREQUENCIES FOR CHECKS. CALTBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTEM 6.
Steam cenerator Level a.
Check S
1, 2, 3 or 5 a.
Comparison or four level indications per generator, b.
Calibrate R
1, 2, 3, h or 5 b.
Known dirrerential pressure applied to sensors.
Bistable trip tester.(U) c.
Test M(Y) 1, 2 or 3 c.
7 Steam Generator a.
Check S
1, 2, 3 or h a.
Comparison of four pressure Pressure indications per generator.
b.
Calibrate R
1, 2, 3, h or 5 b.
Known pressure applied to sensors.
c.
Test M(Y) 1, 2 or 3 c.
Listable trip tester.(U) 8.
Containment Pressure a.
Calibrate R
1, 2, 3, h or 5 a.
Known pressure applied to sensors.
b.
Test M(Y) -
1, 2, 3 or b b.
Simulate pressure switch action.
.'9 Loss or Load a.-
Test P
3 a.
Manually trip 2/h turbine main steam stop valves.
10.
Manual Trips a.
Test P
3 a.
Manually test both circuits.,
11.
Reactor Protection a.
Test M(Y) 1 or 2 a.
Internal test circuits check System Logic Units logic networks and clutch i
power contactors.
j 1
1 0
t
.n.--
.--.,,7
_,nn
-n
. ~,.,
n..
a
i l
TABLE 3-1 (continued)
MINIMUM FREQUE"CIES FOR CHECKS. CALIBRATIO!IS AND TESTING OF REACTOR PROTECTIVE SYSTU4 12.
Axial F ver a.
Check S
1 a.
1.
Comparison of four separate Distribt ion
(>15% pvr) axial index indications.
2.
Comparison of four separate upper trip set point indi-cations.
3.
Comparison of four ceparate lower trip set point indi-cations.
b.
Calibrate R
1, 2, 3, 4 or 5 b.
Known current s applied to in-put of axial shape index cal-culator.
s c.
Test M
1, 2 or 3 c.
Trip test known axial shape index applied to input of axial shape index calculator.
Notes:
(U) The bistable trip tester injects a signal into the bistable and provides a precision readout of the trip set point.
(V) All monthly tests vill be done on only one of four channels at a time to prevent re-actor trip.
(W) Calibrate using built-in simulated signals.
S - Each Shift FQ D - Daily Qg Q - Quarterly SQ R - 18 Months P - Prior to taking the reactor critical if not completed in the previous week (not applicable to a-an 1".
fast trip recovery)
M - Monthly gy 3
c
TABLE 3-2 MINIf31 FREQUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF ENGINFERED SAFETY FFEURES. INSTRUMENTATION AND CONTROLS Operating Mode Surveillance Required Channel Description Function Frequency For Testing Surveillance Method 1.
Pressurizer Pressure a.
Check S
1, 2 or 3 a.
Comparison of four separate Lov pressure indications.
b.
Calibrate R
h or 5 b.
Known pressure applied to sensors and PPLS actuation and blocking logic verified.
j c.
Test M(X) 1, 2 or 3 c.
Signal to meter relay adjusted j
with test device to trip one channel at a time.
Y 4
~4 2.
Pressurizer Low Pres-a.
Calibrate R
h or 5 a.
Part of 1(b) above, sure Blocking Circuit 3.
Safety Injection a.
Test M
1, 2 or 3 a.
Simulation of PPLS or CHPS t
Actuation 2/h logic using built-in test-ing system. Both " standby power".and "no standby power" circuits will be tested for A and B channels. Test vill verify functioning of initia-tion circuits of all equipment normally operated by safety feature actuation signals.
b.
Test R
5 b.
Complete automatic test initiated sensor operation (Item 1(b) or h(b) and including all normal operation.
S.
__c.
i k
TABLE 3-2 (continued)
MINIMUM FREQUE'!CIFS FOR CRECKS. CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROIS Operating Mode i
Surveills. ^ a Required Channel Description Function _
Frequency For Testing Surveillance Method Known pressure applied to R
4 or 5 a.
h.
Containment Pressure a.
Calib" sensors and CPHS actuation High Signal logic verified.
b.
Tect M
1, 2, 3 or h b.
Pressure switch operation simulated one circuit at a time.
5 Containment Spray a.
Test M
1, 2 or 3 a.
Simulation of PPLS and CHPS Logic 2/h logic using built-in
[,
testing system. Both " standby power" and "no standby power" circuits will be tested for A and B channels. Test will verify functioning of initia-tion circuits of all equipment normally operated by safety feature actuation signals.
b.
Test R
h or 5 b.
Complete automatic test ini-tiated sensor operation (Iten 1(b) and h(b)) and including all normal automstic operations.
6.
Containment Radiation a.
Check D
1, 2, 3, b or 5 a.
Verify readings are below upper High Signal alarm initiation radiation level.
-. m
TABLE 3-2 (continued)
MINIfSIM FREQUENCIES FOR CHECKS CALIBRATIONS AND TESTING OF ENGINEERED SAFFTY FEC.URES. INSTRUMENTATION AND CONTROIS Operating Mode Surveillance Required Channel Description Function Frequency For Testing Surveillance Method 6.
(continued) b, calibrate R
1, 2, 3, h or 5 b.
Exposure to known external radiation source.
I c.
Test M
1, 2, 3, 4 or 5 c.
Remote operated integral l
radiation check source used to verify instrumentation, one channel at a time.
7 Manual Safety In-a.
Test R
5 a.
Manual initiation.
I to jection Initiation da l
8.
Manual Containment
.a.
Test R
S a.
Manual initiation.
I Isolation Initiation b.
Check R
5 b.
Observe isolation valves closure.
9 Manual Initiation a..
Test R
5 a.
Manual switch operation; Containment Spray pumps and valves tested separately.
o er E5 10.
Automatic Load a.
Test Q
1, 2 or 3 a.
Proper operation vill be veri-Sequencers fled during safety feature actuation test of Item 3(a) above.
gg.
. -a e
11.
Diesel Start a.
Test M
1, 2, 3 or h a.
Manual initiation followed by
{$
synchronizin6 and loading.
I
TABLE 3-2 (continued)
MINIMUM FREOUT"lCIES FOR CHECKS. CALIBRATIONS AND TESTING OF ENGINEFRED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Operating Mode Surveillance Required Channel Descrintion Function Frequency For Testing Surveillance Method 11.
(continued) b.
Test M
1, 2 or 3 b.
Diesels vill be started prior to safety feature actuation test of 3(a) above.
c.
Test R
5 c.
Diesel start, load shed, syn-chronizing and loading vill be I
verified during Item 3(b) above.
d.
Test P
3, 4 or 5 d.
Diesel auto start initiating circuits.
Y' 12.
Diesel Fuel Trans-a.
Test M
1, 2, 3 or h a.
Pump run to refill day tank.
fer Pump 13 SIRW Tank Low Level a.
Check S
1, 2, or 3 a.
Verify level indication between Signal independent channels.
b.
Test M
1, 2 or 3 b.
A test pressure simulating the tank level is applied to each tank bubbler, one at a time.
c.
Calibrate.
R 1, 2, 3, h or 5 c.
Known level signal applied to sensors and STLS logic verified.
- 14. Safety Injection Tank a.
Check S
1, 2 or 3 a.
Verify that level and pressure i
Level and Pressure In-indications are between indepen-struments dent high and lov alarms for level and pressure.
TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS Operating Mode Surveillance Required Channel Description Function Frequency For Testing Surveillance Method 14.
(continued) b.
Calibrate R
1, 2, 3, 4 or 5 b.
Known pressure and differential pressure applied to pressure and level sensors.
15.
Boric Acid Tank Level a.
Check D
1, 2 or 3 a.
Compare two independent sensors.
b.
Test R
h or 5 b.
Pump tank below low-level alarm point to verify switch operation.
I' c.
Calibrate R
1, 2, 3, 4 or 5 c.
Known differential pressure applied U
to level sensors. At least three points in indicator range vill be obtained-high, middle-of-range, and lov (near alarm set-point).
- 16. Boric Acid Heat a.
Check D
1, 2, 3, 4 or 5 a.
Observe temperature devices for Tracing proper readings.
~s n 17 Steam Generator Lov a.
Check S
1, 2 or 3 n.
Compare four independent pres-k-(
Pressure Signal (SGLS) sure indications.
cm II b.
Test M
1, 2 or 3 b.
Simulated signal.
- ~$
E$
- c.
Calibrate R
k or 5 c.
Known pressure applied to sen-sors to verify trip points, logic
${
operation, block permissive, auto c-reset and valve closures.
i
TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS Operating Mode Surveillance Required Channel rescription Function Frequency For Testing Surveillance Method 18.
SIRW Tank Temperature a.
Check D
1, 2 or 3 a.
Compare two independent temper-Indication and Alarms ature readings.
b.
Test M
1, 2 or 3 b.
Measure temperature of SIRW tank with standard laboratory instru-ments.
i 19 Recirculation Actua-a.
Test R
5 a.
Manual initiation.
tion Switches Y
20.
Recirculation Actua-a.
Test M
1, 2 or 3 a.
Part of test 3(a) using built-in l
M tion Logic testing systems to initiate STLS.
l b.
Test R
5 b.
Complete automatic test initiated sensor operation.
t Notes: -(X) Not required unless pressurizer pressure is above 1700 psia.
(Y) Not required unless steam generator pressure is above 550 psia.
>o S - Each Shift
((
D - Daily a ce M - Monthly Q - Quarterly 1
[j} 5 R - 18 Months P - Prior to taking the reactor critical if not completed in the previous week (not applicable to a U$ "'
fast trip recovery).
3?
TABLE 3-3 MINITSff FTIEQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELIANEOUS INSTRUMENTATION AND CONTROLS Operating Mode Surveillance Required Channel Description Function Frequency For Testing Surveillance Method 1.
Primary CEA Position a.
Check S
1, 2 or 3 a.
Comparison of output data with Indication System secondary CEAPIS.
b.
Test M
1, 2 or 3 b.
Test of power dependent in-sertion limits, deviation, and sequence conitoring systems.
c.
Calibrate R
5 c.
Physically measured CEDM position used to verify system accuracy.
Calibrate CEA position interlocks.
U 2.
Secondary CEA Position a.
Check S
1, 2 or 3 a.
Comparison of output. data with
. Indication System g
primary CEAPIS.
b.
Test M
1 b.
Test of power dependent insertien (All rods out)
Jimit, delvation, out-of-sequence, and overlap monitoring systems.
ci Calibrate R
3 c.
Calibrate secondary CEA position indication system and CEA Interlock Alarms.
3.-
Area and Process a.
Check D
1, 2, 3. !* or 5 a.
Normal readings observed and Monitors internal test signals used to verify instrument operation.
IZI 1, 2, 3,!* or 5 b.
Detector exposed to remote b.
Test M
operated radiation check source.
I 1, 2, 3, Is or 5 c.
Exposure to known radiation c.
Calibrate R
source.
TABLE 3-3 (continued)
MINIM"M FREOUE!!CIES FOR CHECKS, CALIBRATIO?iS A?ID TESTING OF MISCELLANEOUS INSTRUIENTATIO!! AND CO!;TROLS
{
Operating Mode Surveillance Required Channel Eescription Function Frequency For Testinc Surveillance Method h.
E ergency Plan Radia-a, Calibrate A
1, 2, 3, b or 5 a.
Exposure to known radiation tion Instruments source.
b.
Test M
1, 2, 3, h or 5 b.
Battery check, 5
Environmental Monitors a.
Check M
1, 2, 3, 4 or 5 a.
operational check, b.
Calibrate A
1, 2, 3, h or 5 b.
Verify airflow indicator.
6.
Pressurizer Level a.
Check S
1, 2 or 3 a.
Comparison or independent I'
Instru=ents level readings.
b.
Calibrate R-1, 2, 3, b or 5 b.
Known differential pressure f
applied to sensor, c.
Test M
1, 2 or 3 c.
Signal to alarm meter relay adjusted with test device to veri fy setting.
I j
7 CEA Drive System a.
Test R
3 a.
Verify proper operation of Interlocks all CED!! system interlocks, using simulated signals where necessary.
b.
Test P
3 b.
If haven't been checked for tb ee conths & plant is shut-C D A1.
l l
TABLE 3-3 (continued)
Nf MI?II!ra! FREQUENCIPS FOR CHECKS, CALIBRATIONS A'JD TEST!!!G 7
7:
OF !tTSCELLA::Entti Ii:STEUME !TATIO:J A:ID CO!!TR0!S ao y
Operating, Itade j
Survei1 lance Req ui red Channel Description Function Frequency u
For Testing Surveillance Ifethod l
w l
l 8.
Dropped CEA Indication a.
Test R
1, 2 or 3 a.
Insert a negative rate of 1
change pcuer signal to all four power Rance Safety Channels to test alarm.
b.
Test R
3 b.
Insert CEA's belov lower electrical limit to test dropped CEA alarn w
9 Calorimetric Instrtnen-a.
Calibrate H
2, 3, b or 5 a.
Apply known d/p to feed-se tation water flow sensors, w
10.
Control Room Ventilation a.
Test R
1, 2. 3, b or 5 a.
Check damper operation for DFA mode.
b.
Test R
1, 2, 3, h or 5 b.
Check control room for posi-l tive pressure.
11.
Containment Humidity a.
Test R
3, h or 5 '
a.
Elace sensor in a known high Detector humidity atmosphere.
l 12.
Interlocks-Isolation Valves a.
Test R
h or 5 a.
Known pressure of 265 psia on Chutdown Cooling Line applied to pressure trans-mitter and pressure switch and operability of redundant interlock verified.
13.
Control Rocm Thermometer a.
Test R
1, 2, 3, h or 5 a.
Compare reading, with cali-brated thermo: eter.
If not within +20F, replace.
I
1 TABLE 3-3 (continued) 3-S MINIMUM FREQUENCIES FOR CHECKS. CALIBRATIONS AND TESTING q}
OF MISCELTA;EOUS INSTRUMENTATION AND CONTROLS Operating Mode C9 Surveillance Hequired
}q Channel Description Function Frequency For Testing Surveillance Method a.
Compare eight (8) independent lb.
Nuclear Detector Well a.
Test S
1, 2, 3, 4 or 5
\\(
readin gs,
Cooling Annulus Exit d
Air Temperature Detectors b.
Calibrate with known temperature.
b.
Calibrate R
3, 4 or 5 15 Reactor Coolant System a.
Check M
1, 2 or 3 a.
Calculation of reactor coolant flow rate.
Flow Comparison of independent pres-16.
Pressurizer Pressure a.
Check S
1, 2 or 3 a.
sure readings.
os Comparison of independent temper-17 Reactor Coolant Inlet a.
Check S
1 a.
(>15% pur) ature readings.
Temperature 18.
Inv-Temperature Set-a.
Test PM 1, 2, 3 or h a.
Verify operability of actuation circuitry for low-temperature Ioint Power-Operated setpoint power-operated relief Relier Valves valves by utilization of in-stalled test switches.
1 b.
Calibrate R
5 b.
Calibrate temperature and pressure channels.
TABLE 3-3 (Continued)
MINIMUM FPMUEXCIES FOR CHECKS, CALIBRATIONS AND TESTING k
0F MISCEI,I.ANEOU3 INSTRINENTATION AND CCNTROLS S
?
Surveillance Channel Description Function Frequency Surveillance <ethed u,
%)
Note:
(2) Containment area monitor tests / calibrations need only be performed when containment access is permitted.
S - Each Shift D - Daily M - Monthly A - Annually R - 18 Months P - Prior to each startup if not performed within previous week.
y
$(
PM - Prior to scheduled cold leg cooldown belov 3000F; =onthly whenever temperature remains belov 3000F and reactor vessel head is installed.
L e
l TABLE 3 h MINI!E! FREOUE'ICIES FOR SA?? LING TESTS Operating Mode Required Test Frequency Reference For Testine 1.
Ret: tor Coolant (a) Power Operatien Hot Standby (1) Gross B, y, a Radio-3 ti.
/
None 1, 2 or,3, Hot Shutdown activity week week (l)/
(2) Qualitative Ga=ma 3 times Ncne 1, 2 or 3 Spectral Analysis (3) Tritium Radio-Weekly None 1, 2 or 3 activity (h) Chemistry: C1 3 times /
None 1, 2 or 3 week 3 times /
None 1, 2 or 3 02 week (5) Radiochemical Analy-Semiannual (2} None 1
cis for E Deter-mination (6) Boron Concentration Twice/veek Ncne 1, 2 or'3 (b) Cold Shutdown (1) Gross B, Y, a Radio-3 ti=es/
None h
activity week (l)
(2) Qualitative Ga==a Once/veek(1) None k
Spectral Analysis (3) Tritium Weekly None h
(k) Chloride 3 ti=es/
None h
veek (5) Oxygen once/veek None h
(6) Scron Concentration 5 ti=es/
None h
veek (c) Refueling (1) Gross B, Y, a Radio-week (l)/
3 times None 5
Operation activity (2) Qualitative Gamma Once/veek(l) None 5
Spectral Analysis
~
(3) Chloride 3 times /
- None 5.
veek
'(h) Boron Concentration 3 times /
None 5
day Amendment No. 28 3-18
. ~..
t j
4 j
TABLE 3 4 (Continued) 1 MINI!C4 FRFOUE'!CIES FOR S.VfPLING TESTS i
FSAR Operating Mode Section Required l
Test.
Frequeney_-Reference For Tenting i
2.
SIRW Tank Water Boron Concentration Monthly None 1, 2, 3, h or 5 Sample 3.
Concentrated Boric Boron Concentration Monthly None 1, 2, 3, h or 5 j
Acid Tanks k.
SI Tanks Boron Concentration Monthly 5.1.2 1, 2 or 3 5
Spent Fuel Fool Boron Concentration Monthly 9.5 1, 2, 3, h or 5 6.
Steam cencrator Iodine Cencentration Weekly (3)
None 1, 2 or 3 j
Water 7
RWDS Monitor Radioactivity Analysic Prior to Re-11.1 1, 2, 3, k or 5 Tanks and Hotel lease of Each Waste Tanks Batch j
8.
Radioactive Gas Radioactivity Analysis Prior to Re-11.1 1, 2, 3, 4 or 5 Decay Tanks lease of Each Batch
{
9 Stack-cas Iodine 131 and Parti-Weekly (h) 11.1 1, 2, 3, h or 5 l
culate Radioactivity i
j j
(1) When the reactor coolant total specific activity radioactivity level exceeds 50 percent of limits in Specification 2.1.3, the sa=pling and analysis frequency shall be i
increased to a minimes of five times per week. When the total specific activity exceeds 75 percent of this 11:1t, the sa=pling and analysis frequency shall be increased to a minimu= of once per day.
(2) Redeter=ine if: (a) the primary coolant radioactivity increases by more than 10 pCi/cc fro = the previous determinatien, and (b) upon each start-up only after a two-veek equilibrium adjust =ent period shows a 10 pCi/cc increase from the previous determination in accordance with Specification 2.1.3.
Test-ing required cnly during power operaticn.
(3) When steam generator iodine activity exceeds 50 percent of limits in Specifi-cation 2.1.3, the si=pling and analysis frequency shall be increased td a j
minimum of five ti=es per veek. When the steam generator iodine activity exceeds 75 percent of this limit, the sa.=pling and analysis frequency shall be increased to a minimum of once per day.
I i
l l
Amendment No. 28 3-19 J'
TABLE 3-5
~
MINIMUM FREQUENCIES FOR EQUIP!EIT TESTS Operating Mode FSAR Required Section Test Frequency For Testing Reference 1.
Control Ele =ent Drop times of all full-length Each refueling operation 3
T.S.3 Assemblies CEA's
~
2.
Control Element Partial movement of all CEA's Every two weeks 1 or 2 T
Assemblies (Minimum of 6 in) 3 Pressurizer Safety Set point Once each refueling outage h or 5 7
Valves 4.
Main Steam Safety Set point Each refueling outage NA* "
4 Valves Y'
5 Refueling System Functioning Prior to handling fuel on 1, 2, 3, 4 or 5 9.5.6 Interlocks affected equipment 6.
Raw Water System Functioning
, Each refueling outage h or 5 98 Valve Actuation T.
Fire Protection Functioning Monthly 1, 2, 3, 4 or 5 9.11 Pumps & Power Supply 8.
Reactor Coolant Evaluate Daily' 1, 2 or 3
- 4 System Leakage 9
Diesel Generator Fuel Inventory Daily 1, 2, 3 or 4 8.4 Fuel Supply 10a.
Charcoal and HEPA 1.
In-Place Testing **
Each refueling shutdown not 1, 2, 3, 4 or 5 9 10 Filters for Control Charcoal adsorbers and to exceed 18 months or after Room HEPA filter banks shall every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system be leak tested and shall operation or after each com-show >p95 Freon (R-11 plete or partial replacement
- Whenever the system is at or above operating temperature and pressure.
'" Tests shall be performed in accordance with applicable section(s) of ANSI N510-1975 l
I
'""To be performed between hot shutdown and cold shutdown.
Amendmant Tio. 14. Ph
TABLE 3-5 (Continued)
Operating Mode FSAR Required Section Test Frequency For Testing Re ference 10a.
(Continued) or R-112) and cold DOP of the charcoal adsorber/HEPA particulates removal, filter banks, or after any respectively, major structural maintenance on the system housing and fol-loving significant painting, fire or chemical releases in a ventilation zone cou.unicat-ing with the system.
2.
Laboratory Testing **
Price to initial loading in a.
Initial batch tests filter unit.
of activated char-m coal shall show 190% radioactive methyl iodide re-moval when tested under conditions of 195% relative humi-to 0.15 mg/m$ n.05 dity, 1125 F 0 i let methyl iodide con-centration and at a face velocity of with-in +20% of system de-
- sign, b.
Activated charcoal Each refueling shutdown not 1, 2, 3, 4 or 5 cells shall be re-to exceed 18 months or after placed or tested, every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system The test results operation and folleving sig-shall show 190%
nificant painting, fire or methyl iodide re-chemical release ir a venti-moval when tested lation zone communicating under conditions of with the system.
- Tests shall be performed in accordance with applicable section(s) of f>13I N510-1975.
Acendment No. J6, 2h
~..
~
TABLE 3-5 (Continued)
Operating Mode FSAR Required Section Test Frequency For Testing Reference 10a.
(Continued) 295% relative humi-dity, 2,125 F and with-in +20% of system de-sign face velocity.
3.
Overall syr. tem operation a.
Each circuit shall be Ten hours every month.
1, 2, 3, 4 or 5 ope r.Ye.d.
b.
The pressure drop At least once per plant 1, 2, 3, 4 or 5 acrore. the combined operating cycle.
HEPA filters and w
charcoal adsorber d3 banks shall be de-monstrated to be less 1
than 6 inches of water at system de-sign flow rate, c.
Fan shall be shown
- At least once per plant 1, 2, 3, 4 or 5 to operate.within operating cycle,
+10% design flow, h.
Automatic and manual ini-At least once per plant 1, 2, 3, k or 5 tlation of the system operating cycle, shall be demonstrated.
10b.' Charcoal Adsorbers 1
In-Place Testing **
Each refueling shutdown not 1, 2,'3, 4 or 5
~6.2 l
for Spent Fuel De-Charcoal adsorbers shall to exceed 18 months or after 9 10 contamination Faci-be leak tested and shall every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system lity show 3p9% Freon (R-11 or operation, or after each com-R-112) removal, plete or partial replacement of the charcoal adsorber bank, or after any major str+:tural
- Tests shall be performed in accordance with applicable section(s) of ANSI H510-1975.
Amendment No. % 2h
, _ - - - - - -, - - - _ - - - - =. -, -,, - - - -..- -...-- - ~
-.- ~.
~
TABLE 3-5 (Continued)
Operating Mode FSAR Required Section Test Frequency For Testing Reference 10a.
(Continued) 295% relative humi-0 dity, 3,125 F and with-in +20% of system de-sign face velocity.
3.
overall system operation a.
Each circuit shall be Ten hours every month.
1, 2. 3, 4 or 5 1
- operated, b.
The pressure drop At least once per plant 1, 2, 3, 4 or 5 across the combined operating cycle.
HEPA filters and w
charcoal adsorber d,
banks shall be de-monstrated to be less than 6 inches of water at system de-sign flow rate, c.
Fan shall be shown
- At least once per plant 1, 2, 3, 4 or 5 to operate within operating cycle.
+10% design flow.
4 Automatic and manual ini-At least once per plant 1, 2, 3, k or 5 tlation of the system operating cycle, shall be demonstrated.
10b. Charcoal Adsorbers 1
In-Place Testing **
Each refueling shutdown not 1, 2, 3, k or 5
'6.2
~
for Spent Fuel De-Charcoal adsorbers shall to exceed 18 months or after 9 10 contamination Faci-be leak tested and shall every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system lity show 399% Freon (R-ll or operation, or after each com-R-112) removal, plete or partial replacement of the charcoal adsorber bank, or after any major structural
- Tests shall be performed in accordance with applicable section(s) of ANSI H510-1975.
AmendmentNo.}$',2h
TABLE 3-5 (Continued)
Operating Mode FSAR Required Section Test Frequency For Testing Reference 10b.
(Continued) maintenance on the system housing and following signi-ficant painting, fire or chemical release in a venti-lation zone con =unicating with the system.
2.
Laboratory Testing a.
Initial batch tests Prior to initial loading of all charcoal ad-in the filter unit.
sorbers shall show 3p9% elemental iodine o,
b removal when-tested R
under conditions of 295% R.H., 53
>1250F, 5 to 10 mg/
inlet elemental iodine concentration and at the face velocity within +20% of system
- design, b.
The carbon sample Each refueling shutdown not 1, 2, 3, h or 5 test results shall to exceed 18 months or after show >90% elemental every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system iodine removal, operation, and following sig-under conditions of nificant painting, fire or
>95% R !!., >125 F, chemical release in any venti-ito10mg/$3 inlet lation zone communicating with elemental ccncen-the system, tration and within 20% of design face velocity.
A=endment No h, 2h
i TABLE 3-5 (Continued)
Operating Mode FSAR Required Section Test Frequency For Testing Reference 10b.
(Continued) 3.
Overall Systen Operation a.
Operation of each Ten hours every month.
1, 2, 3, 4 or 5 circuit shall be de-monstrated, b.
Fan shall be shown At least once per plant 1, 2, 3, 4 or 5 to operate within operating cycle,
+10% of design flow.
k.
Manual initiation of the At least once per plant 1, 2, 3, k or 5 system shall be demon-operating cycle.
- strated, ta g,
10c. Charcoal Adsorbers 1.
In-Place Testing **
Each refueling shutdown not 1, 2, 3, 4 or 5 9.10 g
for S.I. Pump Room Charcoal adsorbers shall to exceed 18 months or after 6.2 be leak tested and shall every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system show J> 9% Freon (R-ll or operation, or after each com-R-ll2) removal, plete or partial replacement of the charcoal adsorber bank, l
or after any major structural i
maintenance on the system housing and following signifi-cant painting, fire or chemical release in a ventilation zone communicating with the system.
2 Laboratory Testing a.
Initial batch tests Prior to initial loading in I
of all charcoal ad-the filter unit.
sorbers shall show 2995 elemental iodine removal when tested under conditions of 295% R.n., >125*F,
~
5 to 10 mg/m3 inlet
Tests shall be performed in accordance with applicable section(s) of. ANSI N510-1975 Amendment No. J6, 2k
TABLE 3-5 (Continued)
Operating Mode FSAR Required Section Test Frequency For Testing Reference 10c.
(Continued) elemental iodine con-centration and at a face velocity within
+20% of system de-
- sign, b.
The carbon sample Each refueling shutdown not 1, 2, 3, h or 5 test results for the to exceed 18 months or after S.I. Pump Room char-every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system coal filters shall operation and following sig-show no less than nificant painting, fire or 90% elemental iodine chemical release in any venti-remova], under con-lation zone communicating with y
ditions of _95% R.H.,
the system.
at 1250F, 5 to 10 mghS3 inlet elemental iodine concentration and within +20% of design face velocity.
3.
Overall system operation a.
Operation of each Ten hours every month.
1, 2, 3, 4 cr 5 circuit shall be demonstrated, b.
Fans shall be shown At least once per plant 1, 2, 3, 4 or 5 to operate within operating cycle.
+10% of design flow.
4.
Automatic and/or Manual At least once per plant 1, 2, 3, 4 or 5 initiation of the system operating cycle.
shall be demonstrated.
11.
Containment Cool-1.
Demonstrate damper action. 1 year, 2 years, 5 years, 4 or 5 9 10 ing and Iodine Re-and every 5 years there-moval Fuscable Linked after Dampers Amendment No.
, 2h
TABLE 3-5 (Continued)
Operating Mode FSAR Required Section Test Frequency For Testing Reference 11.
(Continued) 2.
Test a spare fuseable link.
12.
Fuel Elements Visually inspect fuel ele-During each refueling outage h or 5 3
cents removed from the re-actor.
13.
Diesel Generator Calibrate During each refueling out.6ge h or 5 8.4.3 i
Under-Voltage i
Relays w
/u 8
I l
l A=endment No. 2h
/
....a_
3.0 SuavEIuANCE REOUIRE*ENTS 3.h Reactor coolant System Intecrity Testing Applicability Applies to test requirements for reactor coolant systen integrity.
Objective To specify test for reactor coolant syste= integrity after the syste:
is closed following normal opening, modification or repair.
Specifications (1)
Whenever the reactor coolant systen is closed after it has been opened, the systen shall be leak tested at not less than 2150 psia prior to the reactor being =ade critical. Operating Mode Required Tor Testir.g: ?erfor=ed when allowed by Techni-cal Specificaticn 2.1.2.
(2)
Whenever modificatiens or repairs are =ade in the reactor coolant syste= that involve new stren6th velds on ec=ponents greater than 2 inch diameter, the new welds shall receive both a surface and 100% volumetric exaninaticn and shril meet all applicable code require =ents., Operating Mode Required For Testing: k or 5 (3)
Whenever =cdifiestions or repairs are made in the reactor coolant system that involve new strength velds on ec=ponents 2 inch dia eter or smaller, the new velds shall receive a surface examinaticn.
Operating Mode Required Fcr Testing:
h or 5 Basis For normal operation, the integrity of the reactor coolant syste=,
in terms of strength, is unchanged.
If the systen does not leak at 2150 psia (operating pressure + 50 psi; +50 psia is normal sys-tem pressure fluctuation), it vill be leak tight during normal oper-ation.
For repairs on ec=penents greater than 2 inch diameter, the thorough non-destructive testing gives a very high degree of confidence in the integrity of the reactor ecolant systen and vill detect any significant defects in and near the new velds.
Repairs on ec=ponents 2 inch diameter or smaller are relatively ninor in co=parison and the surface examination assures a similar standard of integrity.
In all cases, the leak test will ensure leak tightness during normal operation.
MO 3-36
.-_s 3.0 SURVEILLA'!CE RPOUIRE*E TS 35 Containment Test (Continued) the shutdown condition under administrative control and safety procedures defined in the plant operating license.
Operating Mode Required For Testing: 5 (2)
Local Leak Detection Tests (Type B) a.
Testine Recuirements Type B tests are intended to detect local leaks or to measure leakage of primary reacter contain=ent components which seal or penetrate the pressure containing boundary of the primary reactor containment and associated sys-te=s.
Such cc=ponents include:
(1)
Containment penetrations whose design inecrporates resilient seals, gaskets, or sealant ec= pounds, piping penetrations filled with expansion bellows.
(ii)
Air lock door seals, including operating mechanis and penetrations with resilient seals which are part of the ccntain=ent pressure boundary in the air lock structures.
(iii)
Equipment access decrs with resilient seals er gaskets (seal velded doors are excluded).
(iv)
Co=ponents other than those listed in ite=3 1, ii, or iii which'develcp leaks in service and require repairs to meet the acceptance criterion of Type A tests.
Type B tests shall be perfor=ed to detect and =easure local leakage of contain=ent components; acceptable =eans of performing Type B test include:
(i)
Exa=inatien by halide leak detection method (or by other equivalent test =etheds), of a pneu=atic-ally pressurized test chamber censtructed as part of individual contain=ent ec=ponents.
(ii)
Measure =ent of the leakage rate en rate of loss of pressure frc= the pnet=atically pressurized test chamber of the contain=ent co=ponent.
(iii)
Leakage surveillance by means of a permanently installed syste= with provisions for individual or group pressurization of centainment penetra-tion or seals, and =casure=ent of pressure loss l
or air flow through the leak paths.
l t.
All Type B tests shall be perfor:ed by local pneu=atic l
pressurization of the contain=ent ec=ponents, either r
6 3 h0
-nn n--
..,,-n,.
- - ~
--,n
, - -m m y nw--,.,e-.
-.v.w--g.,ene.,-.m.n.-,
e,.
.-mr--
u,
-y
l r
L i
i 3.0 SURVEILLANCE REQUTED'ENTS i
3.5 Containaent Test _(ccntinued) individually or in groups, at a pressure not less than 60 psig except that the personnel access hatch door seals may be tested by pressurizing between the 0-ring seals at 5 psig after each opening or daily, whichever is less a
frequent (Note: Test not required when containment inte-grity not required); the volu=e between the doors shall be leak tested at 60 psig every 6 months. Operating i
Mode Required For PAL Door Testing:
1, 2, 3, h or 5 r
i Detailed supplementary criteria that establish specific test require =ents to fulfill these Specifications are l
provided in reference (3) which is included as an enclo-sure to this Specification.
i i
b.
Accentance Criteria The ec=bined leakage rate of all co=penents subject to i
Type B and C tests shall not exceed 60 percent of L -
I a
c.
Frecuency I
Type B tests except for the personnel access hatch shall be perfor ed during each reae. tor shutdown for =ajor fuel i
reloading but in no case at intervals greater than 2 years.
The access hatch shall be tested at six =enth intervals ;
when it is opened during this interval it shall be tested at 5 psig after each opening or ence each day, whichever l
is less frequent (Note: Test not required when contain-
=ent integrity not required).
t Operating Mode Required For Testing Mechanical (except f
PAL Door, Equip =ent Hatch and Transfer Tube) and Electri cal Penetraticas:
1, 2, 3, h or 5 Operating Mode Required For Testing Equip =ent Hatch and Transfer Tube: h or 5.
(3)
Contain=ent Isolaticn Valves Leaksee Rate (Type C) i a.
Testing Recuirements i
Type C tests are intended to =casure centain=ent isolation valve leakage rate. The valves included are-4 (i)
Containment isolation valves which provide a direct connection with the inside atmosphere i
of the pri=ary reactor contain=ent (including vacuum relief valves and instrument valves).
I i
l (ii)
Contain=ent isolation valves which, in the event
[
of valve leakage or valve =alfuncticn upon cen-tein=ent isolation signal, =ay extend (outside
{
4 3 kl i
=
=.
~
i 3.0 SURVEILLMICE REQUIREME!.*TS r
a
- 3. 5 containment Test (Continued) of containment) the boundary of the leakage-limiting
- I barrier of the reactor primary containment beyond
(
that included during the conduct of T/pe A tests t
l (includes instrument valves in lines connected to the reactor coolant pressure boundary).
l
\\
(iii)
Containment isolation valves in engineered safety systc=s-penetrating containment which, under post-accident conditions, are required to close follow-ing the ter=inat' ion of the safety function.
Type C tests shall be performed by local pressurization.
The pressure shall be applied in the same direction as
)
that when the valve vould be required to perform its safety function, unless it can be deter =ined that the results from the tests for a pressure applied in a dif-ferent direction vill provide equivalent or = ore conserva-tive results.
?/pe B test =ethods may be substituted where appropriate.
I Each valve to be tested shall be closed by normal oper-ation and without any preliminary exercising or adjust-I ments (e.g., no tightening of valve after closure by valve motor).
Detailed supple =entary crite:ria that establish specific 3
I test require =ents to fulfill these Specifications are pro-i a
vided in reference 3 vhich is included as an enclosure to
[
this Specificaticn.
t I
b.
Acceotance Criteria f
[
The combined leakage rate for all co=penents subject to
[
Type B and C tests and subject to the 0.6 La leakaga li=it shall not exceed 60 percent of L
- a t
i If at any ti=e it is deter =ined that a leakage rate is
[
greater than 60 percent of La, repairs shall be initiated r
i==ediately.
If repairs are not completed and conformance f
l to the acceptance criteria is not de=enstrated within h6 i
hours, the reactor shall be shut down and depressurized until repairs are ec=pleted and the local leakage meets l
this acceptance criteria.
l c.
Frequenev
{
t Type C tests shall be perfor ed during each reactor shut-dovn for major refueling but in no case at intervals greater than two years. Operating Mode Required For
(
Testing: h or 5
[
l (1 )
Specific Testine Recuire ents j
1 4
l Any major =cdificaticn or replacement of cceponents of the j
3 h2 i
l l
3.0 SURVEILw:ce RFCUIars:ITs 35 Containnent Test (Continued) primary reactor containment performed after the initial pre-operational leakage rate test shall be followed by either a Type A test, Type B test, or a Type C test of the area affected by the modification and shall meet the applicable acceptance criteria.
(5)
Inspection and Renortine or Tests a.
Containment Inceection A detailed visual examination of critical areas and general inspection of the accessible interior and exterior sur-faces of the containment structures and components shall be performed at each reactor shutdown for a refueling outage and prier to any Type A test to uncover any evi-dence of structural deterioratien which may affect the containment's structural integrity leaktightness. If there is evidence of significant structural deterioration, Type A tests shall not be perfer ed until corrective acticn is taken in accordance with repair procedures, nondestructive examinations, and tests as specified in the construction code under which rules the contain=ent was built. Such structural deterioration and corrective actions taken shall be reported as part of the Type A test report.
Operating Mode Required For Testing:
3 L or 5.
I Report of Test Results l
l g
The initial Type A test shall be the subject of a summary technical report sub=itted to the Cet issien after the conduct of the test.
This report sh111 include a schematic arrangement of the leakage rate =easurement system, the instrumentation used, the supplemental test method, and the test program selected as applicable to the initial test, and all subsequent periedic tests. The report shall contain an analysis and interpretation of the leakage rate test data to the extent necessary to demonstrate the acceptability of the containment's leakage rate in meeting the acceptance criteria.
Periodic test leakage rate results of Type A, B, and C tests that meet the acceptance criteria shall be reported in the licensee's operating report.
Leakage test results of Type A, B, and C tests that fail to meet the accept-ance criteria shall be reported in a separate su==ary that includes an analysis and interpretation of the test data, the least-squares fit analysis of the test data, the instrumentation error analysis, and the structural conditions of the containment cr ec penents, if any, which contributed to the failure in meeting the accept-ance criteria. Results and analyses of the supplemental verification test empicyed to demonstrate the validity of the leakage rate test measurements shall also be in-cluded.
Amendment No. 24 3 k3
5
... i 3.0 SURVEILLANCE REQUIREMENTS I
1 35 containment Test (continued)
(6)
Recirculation Heat Removal Systems I
a.
Testinc Recuirements l
The portion of the shutdcwn cooling system that is out-side the containment shall be tested either by use in normal operation or hydrostatically tested at 250 psig i
at the interval specified in the 3.5(3)a(fii).
operating Mode Required For Testing: Reactor Coolant System temper-4 0
ature less than or equal to 300 F.
l Piping from valves HCV-383-3 and HCV-383 4 to the dis-cnarge isolation valves of the safety injection pumps and containment spray pu=ps shall be hydrostatically i
tested at no less than 100 psig at the interval speci-l fied in 3.5(3)a(iii).
Operating Mode Required For Test-ing: Reactor Coolant System temperature less than o.
equal to 300 F.
[
Visual inspection shall be made for excessive leakage i
from components of the system.
Lyr significant leakage l
shall be measured by collection and weighing or by
[
another equivalent method.
b.
Accettance Criteria
[
l The maxi =um allevable leakage frem the recirculation heat i
re= oval systems' ce=ponents (which include valve stens, flanges and pu=p seals) shall not exceed one gallen per minute, under the normal hydrostatic head frc= the SIR *4 tank.
c.
Corrective Action j
Repairs shall be made as required to =aintain leakage J
vithin the acceptance criteria of 3.5(3)a(ii).
l l
i j
d.
Test Frecuency l
Tests of the recirculatien heat removal system shall be conducted at each =ajor refueling.
j s
(7)
Surveillance for Prestressine System i
a.
Surveillance Reauirements i
Two hundred ten deme tendons and 616 vall tendens are l
provided. These shall be periodically inspected for l
sympte=s of material deterioration or force reduction.
l During each of the first three inspection periods, six
[
dome tendons uniformly spaced in the three layers and l
l seven helical vall tendens in each orientation spaced i
I 3 h4 e
,4--e<,
, ~ - - - -
-<---a w--
r 30 SURVEILLANCE REQUIREMENTS
~
35 cer.tainment Tect (continued) uniformly apart vill be examined. Unless experience in-t dicates othervice, successive inspections vill be per-formed on three dome tendens, cne from each layer, and on three vall tendens of each orientation.
The surveillance tendons shall be inspected as follows:
(1)
Lift-off readings shall be taken on each of the tendens selected to determine the load existing i
in the tenden at the time of inspection. At each surveillance period, readings may also be taken on the load cells of the special instru-
- r mented tendons. Force reductions on the cur-veillance tendens and on the instrumented ten-dons vill be ecmpared.
If goed correlation' exists between these two groups of tendons through several surveillance periods, consideration vill be given to eliminating some lift-off readings and coni-toring of the lead cells as an alternative. Ec h selected tenden shall be ccepletely detensioned and examined for breken vires and any evidence of damage or deterioratien of anchcrage hardware.
(ii)
One wire from each of three helical tendons and one wire of a done tenden shall be removed. Each removed wire shall be carefully examined over its entire length for evidence of cerrosion er other deleterious effects. Tensile tests shall
[
be made en at least three samples cut from each of the four vires removed, one at each end and one at midlength, the samples being of a maxi::ium length practical for testing.
In special cases, the use of fatigue tests and accelerated corrosion tests may be considered.
i (iii)
Ccmparisons shall be made between the quality cen-trol records and each of the surveillance inspecticn i
records for each of the surveillance tendens.
j After completion of the tenden surveillance the individual l
detensiened tendons shall be retensiened to a force ecm-(
mensurate with the average vire stresc indicated by the last lift-off reading for that tenden.
I b.
Accentance Criteria Acceptance criteria for the tendens are as follevs:
(i)
The tendon force determined by the lift-off test shall'be considered adequate if it is not less than the force shown on the appropriate lower li=it curve of FSAR Figure 5.10 4, as adjusted
[
for vire removal, for the elapsed time between i
the original prestressing and the particular l
3 h5
h d
- 3. 0 SURVETI,I.ANCE RECtHRE' TENTS 35 containment Test (continued) l i
surveillance period. These lower limit curves have been generated by calculating the' difference between the anticipated tenden force at end of l
plant life and the minimum tendon force to meet the design requirements. One half of this dir-ference has been added to the anticipated total I
loss of prestress at thc end of plant life and the curves have been drawn to meet this limit.
Since the lock-off force on individual tendons i
is varied to compensate for elastic shortening of the structure, the tenden force at 70% of ulti-mate strength, rather than the actual lock-off-l force shall be taken as the initial prestress force. An allevable limit of not more than one defective tenden out of the total sample popula-tion is acceptable, provided an adjacent tendon on each side of the defective tendon is tested i
and is found to meet criteria. Should cne of the -
I adjacent tendons be also found defective, the Cc= mission shall be notified in accordance with Re6ulatory Guide 1.16, " Reporting of Operating i
Information".
I f
(ii)
No unexpected change ir. corrosien conditions or grease ;roperties.
(iii)
All th2 ee tensile tests en any one wire indicate
[
an ultimate strength at least equal to the speci-fled minimum ulti= ate strength of the vire. If a single test en any cne wire shows an ultimate i
strength less than the specified minimum, the Commission vill be notified in accordance with i
Regulatory Guide 1.16, " Reporting of Operating
}
Information".
f c.
Cerrective Acticn t
If the above acceptance criteria are not met, an i= mediate f
l investigation shall be made to determine the cause(s) for l
the non-conformance to the criteria, and results vill be reported to the Cc=21ssion within 90 days.
d.
Test Frecuency I
j Inspections shall be as follows :
(i)
One year (from date of initial centainment leak rate test)
}
(ii)
Two years l
(iii)
Four years l
(iv)
Every five years thercarter for the life of the 4
plant.
l I
Operating Mode Required For Testing: 1,2,3,bor5 3-46
-,,.-,...g.
,-e
--,..e 3
p-..-.
-r, - -. p
---e
-- r y
e
(8)
End Anchorare Cencrete Surveillnnee a.
Surveillance Pequiremento Specific locations for surveillance vill be chosen from the combined information from the design calculations; the as-built end ccncrete and prestrescing records; ob-servations of the end anchorage cencrete during ano after prestressing; and the results of strain and deformation measurements made during prestreccing and the initial structural test.
The incpections made chall include:
(i)
Visual incpection of the end anchorage concrete exterior surfacca.
(ii)
A determination of the te=peratures of the liner plate area er centaint.ent interior surface in locations nearest to the end anchorage concrete under surveillance.
w-3 L6a
m
- 3. 0 suavEILIA' cE REcuInnE';Ts 3.6 cafety Injection anc centninnent coolinc systems Tests Applienbility Applies to the safety injection system, the containment spray system, the containment cooling system and air filtration system f
inside the centainment.
Objective To verify that the subject systems vill respond prceptly and perform their intended functions, if required.
Speci fiestions (1)
Snfety Injectien Systen Syste tests shall be perfor:ed at each reactor refueling interval. A test safety feature actuation signal vill be applied to initiate operation of the syste=.
The safety injection and shutdown eccling syste= pump motors may be de-energized fer this pertion of the test.
A second overlapping test vill,be censidered satisfactory if centrol board indicatien and visual cbservatiens in-dicate all ecmpenents have received the safety feature actuation signal in the prcper sequence and timing (i.e.,
the apprcpriate pu=p breskers shall have opened and closed, and all valves shall have c:=pleted their travel). Operating Mcde Required For Testing:
5.
(2)
Centainment Frray Syste-a.
System tests shall be performed at each reacter refuel-in3 interval. The test shall te performed with the isolation valves in the spray supply lines at the cen-tainment blocked closed. Cperatien of the syste= is initiated by tripping the ner:al actuation instru=ent-ation. Operating Mcde Required For Testing: 5 l
b.
At least every five years the spray no::les shall be verified to be cpen. Operating Mode Required Fcr Test-l ing: 4 cr 5 c.
The test vill be considered satisfactory if visual observatiens indicate all ec=ponenta have operated satisfactorily.
l d.
Undisturbed samples of Trisodium Fhesphate Dedecshydrate (TSP) that have been exposed to the same environmental conditiens as that in the =ain besKets shall be tested initially and semi-annually on a routine basis.
I 3-Sk Change No. 7 February 28, 197L
I 1
These samples shall have exposed surface areas to mass ratios that are similar to that in the main baskets.
The minimum acceptable cample sise is 0.5 lb.
The samples shall have the same age as the TSP in the main baskets and shall have been exposed to the same en-vironmental history.
If aged samples are not avail-able, the TSP shall be replaced.
(i)
The sample shall first be tested by submersion in a boric acid solution (without mixinc). The concentration of boric acid shall be the same as that found in the borated water storage tank. The temperature of the boric acid shall be equal to or less than that expected during a postulated LCCA. Because the test is to last for several hours (perhaps days) the ten-perature cay be adjusted as a function of tite. The ratio of toric acid (gallens) to TCP (lbs) shall be representative of that presented during a postulated LOCA.
(ii)
Following dissolution of the TSP, the volume of test liquid cbtained in (1) above shall then be mixed. This test shall de=:nstrate that the TSP vill raise the pH of the mixed v...ume test liquid to a value of at least 6 within four hours frca the enset of this part of the test.
Failure to meet the abcVe re-quirenents is reasen to replace the TSP.
Operating Mode Required Fer Testing:
1, 2, 3, h or 5.
~
3-Sha Change No. 7 February 28, 1974 v
n
3.0 ctmvEIux:cE PE':UIRr'E:r:s 3.6 sn ret y injection nnd centnin ent coolinc systems Tests (Cortinued)
(3)
Punos Operating Mode Required For Testing:
1, 2 or 3.
a.
The safety injection pumps, shutdevn cooling pumps,
and containment spray pumps shall be started at in-tervals not to exceed three,menths.
Alternate manual starting between centrol rec: console and the local panel shall be practiced during refueling outages.
b.
Acceptable level: of performance shall be that the pumps start, reich their rated heads at 21-4-"- "e-circulation flow, and cperate for at least fifteen i
minutes.
(b)
Valves a.
The SIR *a' storage tank outlet valves and containment sump isolation valves shall be stroked during the pump test. Operating " ode Required For Testing:
1, 2 cr 3 b.
The SI tank check valves shall be checked for oper-ability during each refueling shutdevn. Operating Mcde Required Fer Testing:
3.
(5)
Centain ant Feeirculatin7 Air cccline and Filterinz Fyrten a.
Energency ecde damper, autcmatic valve, fan, fusible link aute:2 tic damper, and rav vater backup valve operation vill be checked fer cperability during each refueling cutage. C;erating " ode Required Fcr Test-ing: k or 5 s
b.
Each ran and re=ctely operated damper required to functica during accident conditiens vill be exercised at intervals not to exceed three : nths.
C;erating Mode Required For Testing:
1,2,3 Lor 5.
c.
Each air filtering circuit vill be cperated at lea:t 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every scnth.
Operating Mede Required For Testing:
1,2,3,bor5 d.
A visual examination of the HEPA and charecal filters vill be made during each refueling cutage to insure that leak paths do not exist. Operating llcde Re-quired For Testing: h or 5 c.
Messurencnt of pressure drop across the ec=bined HEPA and charcoal adscrter banks shall be performed at least once per plant cperating cycle to verify a pressure drcp of less than 6 inches of vater at systen design flow. Operating Mode Required Fcr Testing:
h or 5.
Amendment No.,'.T, 2h 3-55
4
- 3. 0 SunvEILix cE REQUIRE"E:T3 3.6 sarety Injectien and containment coolinc systems Tests (continued) f.
Fans shall be shown to operate within 1,10% design flow during each refueling outage. Operating Mode Required For Testing:
3, 4 or 5.
g.
Initial laboratory batch tests of charcoal adsorbers shall shev 290% radioactive methyl iodide re= oval when tested under conditions of 2955 relative hu=idity, 12500F, within 1,20% of design face velocity and 5 to 15 mg/m3 inlet methyl iodide ceneentration. A sample chall be recoved for laboratory testing at each refuel-ing outage not to exceed 18 =cnths cr during the next shutdevn following k300 hours of charcoal filtering unit operatien and folleving significant painting, fire or chemical release in any ventilatien sene ec== uni-cating with the system. The results of sample tests shall shov 2,85% radioactive = ethyl iodide removal under the test conditions g.ven above.
Operating Mode Re-d quired For Testing:
1, 2, 3, h or 5.
Basis The safety injection syste= and the centainment cooling syste= are principal plant safeguards that are n,ct cperated during nor=al re-actor operation.
Co=plete systems tests cannot be perferred when the reactor is operating because a safety injectica signal causes contain=ent isolaticn and a centainment spray syste= test requires the syste=
to be temporarily disabled. The =ethod of assuring operability of these syste=s is, therefore, to ec=bine systems tests to be performed during refueling shutdowns in additien to =cre frequent ec=ponent tests which can be perfer=ed during reactor operation.
The refueling shutdown tests demenstrate preper autc=atic operation of the safety injection and containment spray systems. A test sig-nal is applied to initiate autc=atic actien and verificatien made that the ecmpenents receive the safety injecticn actuation signals in the proper sequence. The test demonstrates the opera valves, pu=p circuit breakers, and auteratic circuitry.l}*((g)of the During reacter cperatien, the instrumentation which is depended en to initiate safety injection and containment spray is generally checked daily and the initiating circuits are tested menthly.
In addition, the active ccepenents (pumps and valves) are to be tested every threc =cnths to check the cperation of the starting circuits and to verify that the pumps are in satisfactory running order. The test interval of three
=onths is based en the judgement that = ore frequent testing would not significa:itly increase the reliability (i.e., the probability that the cc penent vculd cperate when required), yet = ore frequent testa vould result in increased vear over a 1cng period of ti=e.
Verification i
I Amendnent:o.[.2h 3-56 1
- 3. 0 SUR7FILLfJ!CE REQUIRWE!!TS 37 Emercency Power Systen Periedic Tects Applienbility Applies to periodic testing and surveillance requirements of the c=ergency power syste=.
Objective To veriR7 that the e=ergency power syste vill respond prc=ptly and properly when required.
Specifications The following tests and surveillance shall be perforced as stated:
(1)
Diesel Generators a.
Each diesel engine shall be started cnce a conth and de-
=enstrated to be ready for leading within 10 seconds (i.e.,
the diesels shall bc tested alternately at two week intervals, not both together). The signal iaitiated to start the diesel shall be varied frc= one test to another to verify all manual and auto start circuits.
This test shall cover all local and re=cte egntrols for both normal and e=ergency =anual conditiens.lll Oper-ating Mode Required For Testing:
1, 2, 3 or k.
b.
Each diesel shall be =1nually started (nor=al start) with all protective devices operable, in preparation for lead-ing onte the bus, ence a =cnth.
With the diesel running at rated speed and voltage, the generator shall be syn-chronized with the L.16 KV bus and the diesel breaker
=anually closed frc= the electrical centrol board. The generator shall then be leades to nameplate rating and allowed to run for 15 =inutes before being off-loaded and the diesel breaker tripped.
Cperating Mede Required For Testing:
1, 2, 3 or h.
c.
Tests shall be cenducted during each refueling outage to de=enstrate the satisfactory overall autenatic cper-atien of each diesel syste=.
This test shall be ini-tinted by the simulated si=ultaneous loss of k.16 K7 supplies to bus lA3 (lAL) and a simulated auto start signal. Proper cperation vill be verified by bus lead shedding and autcmatic starting of selected motors and equip =ent.
Manual centrol of diesel generators and breakers shall also be verified during refueling shut-downs. Operating Mode Required For Testing:
5 d.
Each diesel generator shall be given a thorough in-spectica at least annusily folleving the =anufacturer's recc==endatiens for this class of standby service.
The above tests vill be censidered satisfactory if 6
A=end=ent No. 2h 3-58
3.0 SunvEILIx:ce RErdnPE"E rT3 37 Emergency Povar Syste.9 Pericdie Tests (Continued) all applicable equipment cperates as designed. This vill include calibration of =cnitoring instrumentation.
Operating Mode Required For Testing:
1, 2, 3, 4 or 5 e.
Diesel generator electric loads shall not be increased beyond the centinuous rating of 2500 kv.
f.
The fuel oil transfer pumps shall be verified to be operable each month. Operating Mode Required For Testing:
1, 2, 3 or 4 (2)
Station Batteries a.
Every scnth the voltage of each cell (to the nearest 0.01 volt), the specific gravity, and te=perature of a pilot c911 in each battery shall be measured and recorded.t3)(h) Operating Mode Required Fcr Testing:
1, 2, 3, h or 5 b.
Every three months the specific gravity of each cell, the temperature reading of every fifth cell, and the a=ount of water added shall be measured and recorded.
Operating Mode Required For Testing:
1, 2, 3 h or 5 l
During the first refueling outage end every third re-l c.
fueling outage thereafter the batteries shall be sub-jected to a rated lead discharge test.
Operating Mode Required Fcr Testing:
5 d.
At =enthly intervals the third battery charger, which is capable of being connected to either of the two D.C. distribution buses, shall be paralleled in turn to each D.C. bus.
In each case, lead shall be trans-ferred to this reserve battery charger by svitching out the normal charger. The reserve charger shall be run en load fer 30 =inutes en each bus and the syste shall finally be ret"--a4 'o nor:al.
Oper-ating Mode Required Fcr Testing:
1, 2, 3, 4 or 5 During refueling shutdevns the correct functica of e.
all D.C. e=crgency tr1nsfer switches shall be decon-t strated by =1nual transfer of normal D.C. supply breakers at the 125 volt D.C. distributien panels.
Operating Mode Required For Testing:
5.
(3)
Enerrency Lichtine The correct functioning of the station battery pcVered a.
emergency lighting systen shall be verified at least cnce each refueling.
Operating Mode Required For Test-ing: k or 5 b.
The correct functioning of the battery powered lantern
~
l Amendment No. 24 3-59
3.0 SuavEILLAncE REQUIRFxctTs 37 Enercency Power System Periodic Tests (Centinued) e=crgency lighting systen shall be verified at least
[
once each year. Operating Mode Required For Testing:
1, 2, 3, 4 or 5.
(k) 13.8 Kv Trnnsmission Line The 13.8 Ky trans=iscien line vill be energized and loaded to minimum shutdown requirements at each refueling outage following installation. Operating Mode Required For Test-ing: Reactor Coolant Syrtem temperature less than or equal to 3000F.
Basis The emergency power system provides power requirements for the engineered safety features in the event of a D3A.
Each of the two diesel generators is capable of supplying mini =us required safety feature equipment from independent buses. This redundancy is a factor in establishing testing intervals. The monthly tests specified vill demonstrate operability and load capacity of each diesel generator. The fuel supply and various controls are cen-tinuously menitored and alarmed fer off-ncr=al conditiens. At approximately yearly intervals (durirg refueling shutdevns) autc-
=atic starting en loss of off-site pcver and autc=atic load shed-ding, diesel cennection, and leading vill be verified. At the same intervals, capability vill be verified for manual energency control of these functions from the diesel and svitch-gear rooms.
Considering syste redundancy, the specified testing intervals I
for the station batteries should be adequate to detect and cer-rect any =alfunction before it can result in system =alfunction.
Batteries vill deteriorate with time, but precipitous failure is extremely unlikely. The surveillance specified is that which has been demonstrated over the years to provide an indicatien of a cell becc=ing unserviceable long before it fails.
Referances (1)
FSAR, Section 7.3.h.2 (2)
PSAR, Section 3.h.1 (3)
FSAR, Section 8.3.k (k)
FSAR, Section 8.k.2 Amendnent No. 2h 3-60 9
3.0 SURVEILUJ:CE REQUIRF2E*.~rS
- 3. 8 Main Stem Isolation Valves Applicability Applies to periodic testing of the main stec.m isolation valves.
Objective To verify the ability of the main steam isolation valves to close upon signal.
Specifications The operation of the main steam isolation valves ' 4all be tested during each refueling cutage to demonstra+(e)a closure time of four seconds or less under nc-flev conditiens. 1 Operating " ode Ee-quired For Testing:
L or 5 Basis The main steam isolatien valves serve to limit an excessive reacter coolant systen cocidevn rate and resulter. reactivity insertion following a main steam break incident. Their ability to close upcn signal vill be verified at each schedule.d refuelin6 outage.
References (1)
FSAR, Secticn 10. 3
)
i Amend:::ent No. 2h 3-61 i
t 3.0 SURVEILUJICE REQUIRE'E*!TS 39 Auxiliary Feadwater System Applienbility Applies to periodic testing requirements of the turbine-driven and rotor-driven auxiliary feedvater pumps.
Objective To verify the operability of the auxiliary feedvater syste= and its ability to respend when required.
Specifications (1)
The operability of the motor-driven auxiliary feedvater pump, the stea: turbine-ariven auxiliar/ feedvater p=p, and the auxiliary feedvLcer pumps' stes: generator level regulating valves HCV-1107A, HCV-11073, HCV-110SA, HCV-11083, and auxi-liary feadwater cross-tie valve ECV-13Sh shall be confirmed at least every three Ocnths.
(2)
The capabilities of the motor-driven and turbine-driven auxi-liary feedvater pu=ps shall be verified by using 1ccal pres-sure indicaters and flew indicators in the centrol r0cm. The discharge pressure vill be verified to be h0 psig above the sten: generator pressure at rated steam flow. Operating Mcde Required For Testing:
1, 2 or 3.
Basis The testing every three =cnths of the auxiliary feedvater pu=ps vill verify their cperability by recirculating vater to the energency feedvater storage tcak and operating, one at a time, the regulating valves (ECV-11073 and HCV-11063) to cenfirm a flev path to the stea generators and operability of the valves.
Froper functioning of the stea turbine admissien valve and start-ing of the feedvater p=p vill demonstrate the integrity of the stcom driven pump. Verificatica cf correct operatica vill be made both frc: instrumentation within the main centrol roc: and direct visual observation of the pu=ps.
Re ferences (1)
FSAR, Sectica 9.h i.
3-62 change 'to. 7 February 28, 197h
=
- 3. 0 SURVEILLANCE REQUIREMENTS r
3.10 Reactor Core Parametern Applienbility Applies to reactor core psrameters that affect shutdown margin, MTC, linear heat rate and DN3 mar 6 n.
1 i
Objective l
l To require evaluation of reactor cor e parameters.
I Spec i fication i
The calibration, checking, and tecting specified in the following I
paraCrapha is subject to n.
A maximum allovable extencien not to exceed 25% of the surveillance interval, and b.
A total maximum conbined interval time for any 3 conse-cutive surveillance functienc not to exceed 3.25 times the specified interval.
(1)
a.
The shutdown margin shall be determined:
i J
1.
By verifying that the CEA group withdrawal is above the Transient Insertien Limits of Specification 2.10.2 whenever the reactor is in hot standby or pcVer opera-tion conditions at least cnce per shift, Operating Mode Required for Testing:
1 or 2, or i
i 2.
By considering the following factors whenever the reactor is in hot or cold shutdown at least once per day. Operating Mode Required fer Testing:
3 or h.
(i)
Reacter coolant cysten boren concentration; (ii)
CEA position; (iii)
Reactor coolttnt nystem temperature; (iv)
Fuel burnup; (v)
Xenon concentration; and (vi)
Samarium concentration, b.
The overall core reactivity balance shall be. ccmpared to predicted values to denenstrate aCreement with +1.05 ok/k at 1 cast once per 31 E7?D. The predicted reactivity values ahill be adjusted (normalized) to correcpend to the actual 6
6 Amendment No. /, 7, 32 3-63
0 4
core conditiens prior to exceeding a cycle burnup of 2000
!GD/l*fU after each refuelinc. Operating Mode Required for Tecting:
1, 2 or 3.
(2)
Moderator Temperature Coefficient The MTC chall be deternined at the folleving frequencies and power conditions durin,; each fuel cycle:
1.
Prior to initial operation above 5% of rated power, after each fuel leading. Operatinc Mode Required for Testing.
1 or 2.
2.
At any power level within 500 ZlD/T of initial cpern-tion after each refueling. Operatinc 'sode Required for Testing:
1 or 2.
3 At any power level within 7 EFFD after reaching a rated power equilibria = boren concentratica of 300 ppm.
Operating Mode Required for Testing:
1 or 2.
(3)
Regulating CEA Incertica Limits The position of each regulating CEA group shall be deter-a.
mined to be above the Transient insertien Limit at least once per chift.
Operating Mcde Required for Tecting:
1or 2.
b.
The accumulated times during which the regulating CEA groupe are inserted beyond the Steady State Insertion Limitc but above the Transient :nsertica Limits shall be deterair.ed ence per day.
Operating Mode Require d for Testing:
lor 2.
(b)
Linear Heat Este Menitoring Systems The incore detector mcnitoring system may be used for a.
monitoring the core pcVer dictribution previded that at lenct cnce per 31 daya of acewnulated pcVer cperation the incore detector alarns generated by the plant computer are verified to be valid an.1 satis:y the requirements of the core distributien map.
Operating M:de Required for Test-ing:
1.
b.
The excore detector nenitoring system may be used for monitoring the ccre power distributicn by:
1.
Verifying at least once per 31 days of accumulated power operaticn that the axial shape index, Y, meni-I toring limit cetpoints are maintained within the al-lovable limit s of Figure 2-6, as adj usted by Speci-fication 2.10.4(1).
Cperating Mode Required fcr Testing:
1.
Amendment :!o. 32 3-63a i
9 i
- 3. 0 SURVEIu m:cE REcuins:ErTs 3.10 Reactor Core f'arametern (Continued)
T (5)
Total Integrated and Total Planar Radial Peaking Factors (FR and Fxy9 T
7 FR and Fx shall be determined to be within the limits of Specificatfon 2.10.4 at the following intervals:
a.
After each refueling and prior to cperation above 70 percent of rated power. Operating Mode Required for Testing:
1 (1705 pover).
b.
At least cnce per 31 EFPD's of accumulated power opera-tion. Operating Mode Required for Testing: 1 ( >40% pover ).
(6)
Azimuthal Power Tilt (T )
q Whenever the core power is above 7C1 of rated power, the axi-tuthal power tilt shall be oetermined to be within its limits by calculating the tilt at least once every day using either,
Operating Mode Required for Testing: 1 (>704 pover):
a.
The execre detectors with at least fcur safety channels or two symetric safety channels and two sy=etric centrol channels operable, or b.
The inccre detectors with at least two strings of three rhodium detectors per full core height quadrant operable.
t (7)
DNB Parameters I
a.
The cold leg temperature, pressuri:cr pressure, and axial shape index shall be verified to te within the limits of Table 2.6 at least cnce per shift.
Operating Mode Required for Testing:
1 (>15% power).
b.
The reactor vessel coolant total ficv rate shall be deter-mined to be within its limit by measurement at least cnce
.i per =onth.
Operating Mode Required for Testing:
J., 2 or 3 i
i I
l Amendment No. 32 3-63b
.~.
o e
j
+
30 SimVEILIE!CE REQUIREEITS 3.11 Environmental,Radioloreical Monitorins'
)
Applicability l
r I
Applies to routine testing of plant environs.
l J
Objective To establish a sampling program which vill provide recognition of l
changes in radioactivity in the environs.
I i
{
Specifications (1)
Collection of Environ-ental Samnles I
Operating Mode Required For Testing:
1, 2, 3, k or 5 En-t viron= ental samples vill be taken according to the follev-j ing schedule:
i i
i TABLE 3-9 SA'4PLE TYPES A!ru FREQUE* ICY r
Collection Analysis No. of Sa=nle Class Frecuener FrecOency Sa=cles Location j
l Background Radiation Film or TLD Q
Q 10 Fig. 2.10-1 FSAR G-M Survey Q
Q 15 Fig. 2.10-2 FSAR
'l Surface Water W
M 4
Fig. 2.10-2 FSAR Well Water M
Q h
Fig. 2.10-2 FSAR t
Mud and Silt A
A 1
Fig. 2.10-2 FSAR 1
Fish A
A 6
Fig. 2.10-2 FSAR i
Milk W&Q W&Q 3
Fig. 9.10-2 FSAR i
Vegetation A
A 6
Fig. 2.10-2 FSAR j
Air Particulate W&M W&M k
Fig. 2.10-2 FSAR l
Wildlife A
A 1
Fig. 2.10-2 FSAR Precipitation M&Q M&Q l
Fig. 2.10 2 FSAR Soil A
A 3
Fig. 2.10-2 FSAR
-l 1
Cattle Feed Q
Q 2
Fig. 2.10-2 FSAR i
A = Annually M = Monthly Q = Quarterly W = Weekly (2)
Radionetivity Limits [
l I
Operating Mede Required For Testing:
1, 2, 3, b or 5. -The limits listed below and the sensitivities in Table 3-11 vill be used for the samples listed in Table 3-10.
i s.
Air Particulate l
When a gross beta count' reveals casanctivity in excess of 10-12 pCi/nl er 1 pCi/m3, a ga==a spectral analysis vill be perfor:ed. A gn=ma spectral analysis vill be carried out en monthly ccaposite of the weekly sa ples.
Iodine cartridges at air particulate stations will be i
analyzed for iodine-131 veekly.
l I
Amendment No. 28 3 6h i
4 3.0 suavEILIAnct REcu!PE' m s 3.12 Badioactive Msterials Applienbility Applies to the periodic test and record requirements and sampling and monitoring =cthods used for facilities effluents.
Objective To ensure that radicactive liquid and gaseous releases frcs the faci-lity are maintained as lov as practicable and within the Ifmits speci-fied by Specifications 2 9(1) and 2.9(2).
Speci fi catien s (1)
Liquid Effluents Operating Mcde Required For Testing:
1, 2, 3, h or 5.
a.
Facility records shall be maintained of the radioactive concentrations and volume before dilutien of each batch cf liquid effluent released and of the avera6e dilution flew and length of time over which each discharge occurred.
b.
Prior to release of each batch of liquid effluent, a sample shall be taken from that batch and analyzed in accordance with Table 3-11.
c.
Radicactive liquid vaste sa=pling and activity analysis shall be perferred in accordance with Table 3-11.
~
d.
The liquid effluent radiation =cnitcr shall te calibrated at least quarterly by means cf a check source and annually with a kncun radicactive source.
Each =cniter, as des-cribed, shall also have an instru=ent channel test =cnthly and a sensor check daily.
c.
The status and perfernance of autesatic isolatica valves and discharge tank selectica valves and results of inde-pendent liquid vaste sa ples shall te checked and logged.
I 3-69 Anendment No. 28
I
- > - ~
3.0 simVETURicE RECUIRE"E!;TS 3.12 Radionettve rasterials (Continued)
Basis The surveillance requirements given under Specification 2.9(1) pro-vide assurance that liquid vastes are properly controlled and moni-tored during any planned release of radioactive materials in liquid effluents. These surveillance require =ents provide the data for the licensee and the Cc==icsion to evaluate the statien's perfor=ance relative to radioactive liquid vastes released to the environment.
Reports on the quantities of radioactive caterials released in liquid effluento chall be furnished to the Cc==issico on the basic of Section 5.6 of these Technical Specifications. On the basis of such reports any additional information the Cc==issica =ay obtain frc= the licensee or others, the Cc==icsien may fro = time to time require the licensee to take such acticn as the Oc==icsion dec=s appropriate.
(2)
Airborne Effluents a.
Gross radioactivity of gaceous effluents shall be conitored and recorded to enable release rates of gross radioactivity to be determined on an hourly basis. Operating Mode Re-quired For Testing:
1, 2, 3, 4 or 5.
b.
Radioactive gasecus vaste sampling and activity analysis shall be performed in accordahce with Table 3-12.
c.
The vaste gas holding tank effluent =cnitor shall be tested prior to any release of radioactive gas frc= a holdup tank and shall be calibrated at refueling intervals. The cali-bratica procedure shall censist of expcsing the detecter to a referenced calibratien ecurce in a centro 11ed reprc-ducible gec=etry.
The source and gec=etry shall te re-ferenced to the original menitor calibration which prevides the applicable calibration curves.
Operating Mode Required For Testing:
1, 2, 3, h or 5.
d.
Gases discharged through the stack shall be continuously monitored for gress noble gas and particulate activity.
Whenever either of these =enitcrs is inoperable, appro-priate grab camples shall be taken and analyzed daily.
Operating Mode Required For Testing:
1, 2, 3, h or 5.
l e.
During power operation, the condenser air ejector discharge shall be centinuously =enitored for gross radiogas activity.
Whenever this =cnitor is incperable, grab camples chall be taken and analyzed for gross radicactivity (S,y) and the ratio of long-lived (greater than eight days half-life) to short-lived radioactivity determined at least five days per veek and whenever the pri=ary coolant gross radioactivity or the unidentified leak rate increases by a factor of two.
Operating Mode Required Fcr Testing:
1.
g 3-70
l e
3.0 ctanttix:cr ammneerrs 3.12 Radiosctive Msterials (Continued) f.
When the seecndary system iodine concentration is greater than 25 percent of the limit specified in 2.1.3 (Secondary Coolant Limit), camples frc the air ejector shall be taken at Icast weekly. At the sa e time, a determination of the iodine partiticn factor for the blowdown tank shall be made. Operating Mode Required For Testing:
1, 2 or 3 l
g.
Facility records of iodine and particulate releases with half-lives greater than eight days shall be =aintained on the basis of all iodine sampling devices and particu-late filter analyses.
h.
Records shall be maintained and repcrts of the campling and results of analyses shall be nutmitted in accordance with Sections 5.6 (Plant Reporting Requirements) of these Specificctions.
Basis The surveillance require =ents given under Specificatica 2.9(2) pro-vide assurance that radicactive gaseous effluents frc the station are properly controlled and monitored over the life of the station.
These surveillance requirements provide.the data for the licensee and the Cetnissicn to evaluate the performance of the station rela-tive to radioactive gasecus vastes released to the environ =ent.
Reports en the quantities of the radioactive =aterials released in gaseous effluents shall be furnished to the Cen=ission on the basis of Sectica 5.6 of these Technical Specificatiens. On the basis of such reports and any additional information the Cc ission =ay ob-tain fron the licensee er others, the Cc==issica =ay frc time to time require the licensee to take such action as the Cc mission dee=n apprcprl:te.
3-71
A TABLE 3-11 RADIOACTIVE LICUID UAS"'E SA"PLI'IG A*iD A'IALYSIS A.
Monitor & Hotel Unste Tanks Releases Operating Mode Required For Testing:
1, 2, 3, h or 5.
Type of Sensitivity of Sampline Frequency Activity Analysis Analysi s Each Batch (3)
_Princital Ganna Emitters 5 x 10-7 uCi/ml Dissolved Nnble Gsses.
I 10-" uCi/n1 i
Pa-1LO, La-1~0, I-131 i
10-0 pCi/n1 Monthly Procortional Compositell)
_H-3 10-5 uCi/=1 Gross a 10-1 uCi/ml crtional Sr-89, Sr-90 10-8 uCi/=1 QuarterlyProI Cetrosite(l B.
Secondarv Plant 31cvdown and Leaksce Peleases(2)
Cperating Mode Required For Testing:
1, 2 or 3 Type of l Sensitivity of Se pline Frequancy Activity Analysis I
An alysi s Weekly
_Princiral G1nns Enittern 5 x 10-7 uCi/ml
_Ba-lh0, L1-lh0. T-111 10-0 uCi/nl Dissolved :loble Cases 6
10-" uCi/n1 MnthlyPrepg-)tional 10-5 uCi/n1 Cc positel
_H-3 Oross a 10-1 uCi/ml i
Quarterly ? ppertional Sr-S9, Sr-90 10-8 pCi/=1 Cerrosite */
N07FS:
(1)A proporticnal cr.mple is one in hich the quantity of liquid sampled is propertional to the quantity of liquid vaste discharged frca the plant.
A=endment No. CS 3-72
O s
3 TABLE 3-12 RIDICACTIVE CACECUS 'JASTE S A!GLI?iC A'!D A?!ALYSIS A.
Gac Decay Tank Felesces Operating Mode Required For Testing:
1, 2, 3, h or 5 Sampling Type of Sensitivi of Sample Tyne Frequency Activity Analycis Analysic
)
Gas Each Tank Gross Ganna 10-5 pCi/cc Release Individual Gazza Emitters 10 b pC1/cc(2)
B.
Containment Vent in:- Felances (*.then ecntainment integrity is required)
Operating Mode Required For Testing:
1, 2, 3, h or 5 Sampling Type of Sencitivi of Samnle ?me Frecuancy Ac',1vity Analysis Analysin Gas Each Vent Gross Gamma 10-5 pCi/cc Individual Ganna E:nitt ers 10 b pCi/ce(2)
Echumidified Sample Each Vent H-3 10 6 pCi/cc C.
Condenser Air Ejecter Palesres Operating Mode Required For Testing:
1, 2 er 3 Sampling Type of Sensitivity of Sample Spe Fraquency Activity Analysic An rtlysi s Gas Monthly Gross Garza 10-pCi/cc Individual Gas a E=itters 10-3 pci/ce(2)
e
~,
TABLE 3-12 RADIOACTIVE GASEOUS VASTE SA"?LIi!G A'TD A'TALYSIS (Continued)
D.
Stack Pelences Operating !! ode Required For Testing:
1, 2, 3, h or 5 Sampling l
Type of Sensitivity)of Analysi s (l Activitr Analysic Samnle Tyne Frecuenev Gas Quarterly
_ Gross Ga-ra 10-b uCi/cc Individual Ga==a 10-5 uCi/ec(2)
E::itters Dehwaidified Each Lecay ;
samnie Release H-3 10-6 uCi/ce t
I-131. I-133 l3x10-12 uCi/ce Charecal Veekly i I-135 Weekly Cross 8.y 3 x 10-12 uCi/cc Ba-140, La-140, Weekly I-131 3 x 10-11 uCi/ce
!-fonthly Co=posite Cross 8,y 3 x 10-12 uCi/cc of Veekly Individual Ga==a Particulates Sa-ules E-itters 3 x 10-11 uCi/cc Quarterly Composite Sr-89, Sr-93 1 x 10-11 uCi/cc of Weekly Samples One Weekly Sa=ple per Cross a 3 x 10-12 uci/cc Quarter NOTES:
(1) The above activity analysis sensitivities are based en the projected capability of laboratory instrumentation and techniques to be e.. ployed by Fort Calhoun.
In order to assure that actual Fort Calhcun cperating experience is utill:ed, a reevaluatien vill be perforced within two years of initial full pcVer operation of the plant.
For certain mixtures of gn==s e=itters, it =ay net be possible to measure radienuclides at levels near their sensitivity limits when other nuclides are present in the sa=ple at =uch higher levels. L'nder these circu= stances, it vill be more apprcpriate to calculate the levels of such radienuclides using observed ratios with those radio-nuclides which are =easurable.
i 3-75 k
a 3.0 SURVEILUJ!CE REOUTRE'EIT3 3.13 RADIbACTIVE 5'ATERI AL SOURCES SURVEILLA*!CE Applicability _
Applies to leakage testing of byproduct, source, and special nuclear radioactive material scurces.
Objective To assure that leakage from byproduct, source, and special nuclear radioactive material scurces does not exceed allovable limits.
Specification Tests for leakage and/or centamination shall be performed by the licensee or by other persons specifically authorized by the ZiRC cr an agreement State, as follows :
1.
Each sealed source, except startup sources subject te cere flux, containing radioactive material, other than Hydregen 3, with a half-life greater than thirty days and in any for= cther than gas shall be tested for leakage and/cr conta:ination at intervals not to exceed six months.
2.
The periodic leak test required does not apply to sealed sources that are stered and not being used. The sources excepted frc:
this test shall be tested fer leakage prior to any use or trans-fer to ancther user unless they have been leak tested within six mont'.s prior to the date of use or transfer.
In the ab-sence of a certificate frem a transferer indica:ing that a test has been made within six months prier to the transfer, sesled sources shall not be put into use until tested.
3 Startup sources shall be leak tested prior to and folleving any repair or =aintenance and before being subjected to core flux.
Operatinc !! ode Required For Testing:
1, 2, 3, L or 5 l
Amend:ent No.11 3-76 Dated: Feb. h, 1976
30 SunvE7uxicE REcu1REMENTs 3.15 Fire Protecticn Systen i
_ Applicability Applies to fire detection and fire extinguishing subsystens in nue-lear safety related areas and other areas which may impact on safety related systems.
Objective To ensure the operability of the fire protection system in nuclear safety related systems. Surveillance frequencies specified below Shall have a tolerance of +254.
Spaci fications (1)
Each fire detector listed in Table 2-7 and in containment shall be deconstrated cperabic; a.
At least once per 6 =cnths by performance of a channel functional test and a test of the supervicien circuitry.
Operating Mode Pequired for Testing:
1,2,3,bor5 l
b.
Testing interval for fire detectors which are inaccessible due to high radiation or require an equipment alignment not used in power cperation may be extended until such time as the detectors becere accessible fcr a minimum of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. However, the shutdown need not be extended solely for the purpcse of this testin5 Such detectors shall be functionally tested at a maximum interval of once per refueling cycle. Operating Mode Required for Testing:
3, k or 5 (2)
The fire suppression water syste= shall be demonstrated cper-able:
B a.
At least cnce per =cnth by starting each pump and oper-ating it for at least 15 =dnutes.
Operating Mode Required for Testing:
1, 2, 3, h or 5.
b.
At least cnce per =cnth by verifying that each valve in the flow path is in its correct position.
Operating Mode Required for Testing:
1, 2, 3, h or 5 c.
At least once per 12 ncnths by cycling each testable valve (those which can be cycled withcut endar.gering the safety of equipment) in the flev path through at least ene com-plete cycle of fall travel. Operating Mode Required for Testing:
1,2,3,hcr5 i
d.
At least once per 13 =caths by performing a pystem func-ticnal test which includes:
Amendment No. ho 3-80
- 3. O SURVEII.I.ANCE REOUIR MENTS 3.15 Fire Protection System (Continued) i 1.
Verifying that each pump develops at least 1800 cpm at a system head of 260 feet, Operating Modes Re-l quired for Testing:
2, 3, k or 5.
2.
Cycling each valve in the flow path that is not test-able during plant operation throuCh at least one com-plete cycle of full travel, Operating Modes Required for Testing:
3, k or 5, and 3.
Veriry that each fire pump starts automatically on lov fire systen pressure to naintain the fire sup-pressien water system pressure >100 psig, Cperating bbdes Required for Testing:
1, 2, 3, h or 5.
e.
At least cnce per 3 years by performing a flow test of the system in accurdance with Chspter 5, Section 11 of the Fire Protection Handbock,1kth Edition, published by the unticnal Fire Protection Associatien using a clean water source. Operating Itde Required for Testing:
1, 2, 3, 4 or 5 f.
At least once per year by visus 11y inspecting the strainer on the discharge side of the fire pumps to verify operability.
Operating Mede Required for Testing:
1, 2, 3, k or 5 I
(3)
The sprinkler system in the Diesel Generator Roon shall be de-monstrated to be operable:
a.
At least once per 18 months:
1.
By visual inspecticn of the spray headers to verify their integrity.
Operating "cde Required for Test-l ing:
1, 2, 3, k or 5.
I 2.
By visual inspecticn of each nossle to verify no bicekage. Operating Mcde Required for Testing:
1 1, 2, 3, k or 5 t
I b.
At least once per 3 years by performing an air flow test through each cpen head spray / sprinkler header and verify-ing each open head spray / sprinkler nossle is unobstructed.
Operating Mode Required for Testing:
1, 2, 3, 4 or 5 (k)
Each fire hose station designated in Table 2-6 chall be veri-fled to be operable:
a.
At least once per month by visual inspection of the statica 4
to assure all equipment is available and the systen pres-sure (ar determined at the jockey punp pressure gauge) is within 13 mits. Operating Mode Required for Testing:
1, 2, l
3, 4 or 5 b.
At least once per 18 nonths by reteving the hose for in-spectien and repacking and replacing all caskets in the couplings that are degraded.
Operating Mode Required for l
Testing:
1, 2, 3, 4 or 5.
I Amendment No. 40 3_31
c
- 3. 0 CURVEILTRICE REQUIREME!:TS 3.15 Fire Protection Systen (Continued) c.
At least once per 3 years by:
1.
Partially opening the hose s ation valves to verify e
valve operability and no blockage.
Operating Mode Required for Testing:
1, 2, 3, h or 5.
l I
2.
Conducting a hose hydrostatic test in accordance j
with '!FPA requirements. Operating Mode Required ror Testing:
1, 2, 3. k or 5 (5)
Penetratien fire barriers shall be verified to be functional (intact) by a visusi fnspecticn:
a.
At least once per 18 months. Operating 5bde Required for Testing:
1, 2, 3, 4 or 5 b.
Prior to declaring a fire penetration seal functional following repairs or maintenance.
Operating Mode Required for Testing:
1,2,3,4or5 (6)
The dL'sel fire pur.p shall be de=cnstrated CPERA3LE:
a.
/.t least once per month by verifying that the fuel storage tank contains at least 200 gallens of fuel. Operating Mode Required for Testing:
1, 2, 3, k or 5 l
b.
At least cnce per quarter by verifying that a sample of diesel fuel from the fuel storage tank, obtained in ac-cordance with ASTM-02TC-65, is within the acceptable limits specified in Table 1 of ASTM-D975-Th with res-pect to visecsity, vater content and sediment. Operating 2bde Required fcr Testing:
1, 2, 3, k or 5.
At least once per 13 months, during shutdown, by subject-c.
ing the die:ci to an inspoeticn in accordance with pro-cedures prepared in conjunction with its manufacturer's recor.mendaticna for the class of service. Operating Mode Required for Testing: k er 5 1
(7)
The fire pump diesel starting 2h-volt battery bank and charger l
chall be demonstrated CPERABLE:
a.
At least once per month by verifying that the electrolyte level of each battery is above the plates. Operating Mode I
Required for Testing:
1, 2, 3, h or 5 i
b.
At 1 cast ence per quarter by verifying that the specific gravity is appropriate for centinued service of the bat-t e ry. Operating Mode Required for Testing:
1,2,3,h or 5.
At least once per 1S months by verifying that:
c.
I Amendment tio. 38 3-82 A
y_
_y
3.0 cunvEIrunCE RE0tnREMr' TC 3.15 Fire Protection Cynten (Ccntinued) j 1.
The batteries and battery racks chow no visual in-dication of physical damage or abnormal deteriora-tion.
Operating :!ade Required for Testing:
1, 2,
- 3. L or 5.
2.
The battery-to-battery and terninal connecticns are clenn, ticht, essentially free cf corrosion and suit-able corrosion protectica is used.
Operating !! ode l
Required for Testing:
1, 2, 3, h or 5 l
l Ranin i
The fire protection system provides r. = cans for detecting, alar =-
ing, and extinguishing plant fires. The syste= is divided into l
l the fire detection subsystem and fire extinguishing subsyste=,
The fire detection subsystem is an instrumeritatien system which alarms control room operator: of a fire, indicating fire loca-tion on a panel in the centrol roan, and providing Iccal indi-cation from the detector in the affected zone.
The fire extinguishing system include: the sprinklers which pro-tect the Diesel Generator Rooms.
Also included are the hose stationc which protect the immediate vicinity outside the entire plant, hose cabinets inside the intake structure, and other mic-cellaneous equipment.
Maintaining the operability of the fire protection cy: ten under various operating conditions is essential to incure the integrity of various nuclear safety related plant systems and e ;uipment.
The above curve 111ance measures aid in accomplishing thic objective.
Specificatien 3.15(2)f. provides a surveillance program that incures that eilt and other caterial in the river water vill not prevent the delivery of vater to areas protected by fire water suppression systens.
Amendment No, ho 3-S3 I
i og..o s
/
2.2 Monitorinc and Banortinc en Loss of Biota by Imoine ement Applienbility This applies to fish and cther fauna impince-1 on the cooling water intake screens.
Objective To evaluate the loss of aquatic life due to operation of the station so as to take corrective action if needed.
Speci ficat iens 1.
Fish and other aquatic fauna impinged on the travelling screens shall be identified by species, size and quantity, and the data-recorded in tabular form. One of the six travelling screens vill be sa pled daily for cne hour. During the su==er (May-September) of the first year of opr. ration, an additicnal 1-hour sa=ple shall be taken each ni ht.
- hese data shall be summarized l
i 6
and reported to the Directorate of Licensing semiannually, as I
discussed in section 5.
Incidents of large numbers killed due l
to operation of the staticn shall be repcrted to Regica IV, Directorate of Regulatory Operations, within 2h hours by tele-s phone or telegraph; and data concerning any such incident and its probable cause shall be included in a detailed report to DL within 10 days. Operating Mode Required For Testing:
1, 2, 3, b or 5 (when circulator in operction).
2.
The method described in 1. =ay be used en a reutine basis once it is statistically shovns that the one hour per day ss=ple of screens is an adequate representation of the daily impingement.
Basis The preoperatienal and operaticnal monitoring prcgra=3 should be used to deter =ine specific numerical limits for this parameter.
- However, sufficient baseline information is net available to determine this limit.
This special study is designed to deter =ine that no long-ter: ad-verse changes are cecurring in the ecosyste: frc plant operatien.
It should also provide the type of infor:atien needed to determine an operating limit or establish that the impingement study is no longer needed dur to an insignificant impact.
2.2-1
_ _ _ _ _ _ _.. _. - - _ _. - - - - - -