ML20199L882

Amend 110 to License DPR-21,modifying Tech Specs Re Disarming Control Rods When Refuel Interlocks or Reactor Protection Sys Trip Functions Inoperable

ML20199L882
Person / Time
Site:	Millstone
Issue date:	04/04/1986
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:
Shared Package
ML20199L878	List: ML20199L873 ML20199L882 ML20199L887
References
NUDOCS 8604100466
Download: ML20199L882 (13)

Text

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~,, UNITED STATES

! n NUCLEAR REGULATORY COMMISSION f

• i WASmNGTON, D. C. 20555 THE CONNECTICUT LIGHT AND POWER COMPANY WESTERN MASSACHUSETTS ELECTRIC COMPANY AND NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 DOCKET NO. 50-245 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 110 License No. OPR-21

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by the Connecticut Light and Power Company, Western Massachusetts Electric Company, and Northeast Nuclear Energy Company, (the licensees) dated October 30, 1985, complies with the standards and requiremer,ts of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the

- provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

8604100466 860404 DR ADOCK 0500 5

2. Accordingly, the license is amended by changes to the technical specifications as indicated in the attachment to.this license amendment and Paragraph 2.C(2) of Provisional Operating License No. DPR-21 is hereby amended to read as follows:

(2) Technical Specifications The technical specifications contained in Appendix A, as revised through Amendment No.110, are hereby incorporated in the license.

The Northeast Nuclear Energy Company shall operate the facility in accordance with the technical specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAP REGULATORY COMISSION f -

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LbAAAtq*%M _L .

Christopher . Grimes, Directo Integrated Safety Assessment Project Directorate Division of PWR Licensing - 8

Attachment:

Changes to the Technical Specifications Date of Issuance: April 4,1986 0

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ATTACHMENT TG LICENSE AMENDMENT NO.110 -

PROVISIONAL OPERATING LICENSE NO. DPR-21 ,

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, DOCKET NO. 50-245 4

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT 3/4 1-la 3/4 1-la i

. 3/4 1-2* 3/4 1-2*

3/4 1-3* 3/4 1-3* '

3/4 1-4 3/4 1-4 3/4 10-1 3/4 10-1 3/4 10-2* 3/4 10-2*

B 3/4 1-3 B 3/4 1-3 8 3/4 1-4* B 3/4 1-4*

B 3/4 10-1 B 3/4 10-1 B 3/4 10-2* B 3/4 10-2*

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• Overleaf pages provided to maintain document completeness.

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LIMITitG GNDrrICN EUR QUATICN SURWJIDN2 BEQUIRDENT D. When the reactor mode switch is in REETEL or

SUID0hN and fuel is in the reactor vessel, no trip functions are required to be q =r=hla poovided that all ocntrol rods are fully insertad, and either electrically w hydra.alically dimannart. 'Ihereafter, I daily surveillanos shall be performed to verify

• that all control rods renain valved cut or

! electrically <ti==nnart.

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l Millstone - Unit 1 3/4 1-la , Amendment No. JNf.110

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i Asie 14, 1984 IOCIOR Pf01ECTIQ4 SEIEM (SOAM) I!EIRMNTATIN RBQUIIDENIS .

Mininun Nunter -

of Operable Mades in which Ebnctim Inst. Oumels Trip Rriction Trip Ievel Setting Mat Be Operable Action

• per Trip (1) IUUEI/ SIRRItPADr Syston SUITON (8,11) SIN G f Run 1 Ftxh Switch in SUlIDN X X X A .

s 1 Marual Scram X X X A i

IIN:

High Flux X X (5) A 3 1120/125 of full scale A 3 Inoperative A. HI Voltage < 80 volt DC X X X (10) ,

B. IIM Madale tk1 plugged l C. Selectx Switch not in  !'

Operate Ibsiticn APIM:

2 Flow Blased High Flux See Secticn 2.1.2A X X X A or B -

2 Recboed High Flux See Section 2.1.2A X X X A or B 2 Incperable A. >50% IFIM Inputs ** X X X A or B B. Cirulit Board 14 moved C. Selector Witch not in Operate Ibsiticn 2 High Ibactor Pt-re 11085psig X X X A 2 High Drywell Pressure 12psig X (9) X (7) X (7) A X X X A 2 asactor Iai Water Iavel11.0 inch ***

2 Scran Discharge Vol. X (2) X X A 126 inches above the center- -

High Level line cf the lower end c@

• to SDIV pipe weld 2,'4 1-2 "M1* * -'W*1 Amenchent No. 98

Jura 14, 1984-

• DBm 3.1.1 (Cbntirued)

REACIOR P!UI!LTICN SYSIIM (SOAM) DEIRMNTATICN REQJIREMNIS ,

Mininun Rmber of @rahle Modes in which Puncticn Inst. Gamels Trip Ebnction Trip I.evel Setting Mtst Be Operable Acticn*

per Trip (1) REFUEI/ STARIUPAUT Systen SUIIDN (8,11) STAMBY RN 2 Turbim Con &nser Irw >23 in. hg. Vamtsa X (3) X (3) X AcrC Vacutzn 2 Main Steamlim Radiaticn p x Nonnal Ebll Ibwer - X X X A cc C Badarund 4 (6) min Steanlim Isolaticn <10% Valve Closure X (3) X (3) X A or C Valve Closure 2 'Ibrbine Ocntrol Valve See Secticn 2.1.2 F X (4) X (4) X (4) A ce C Fast Closure 2 'Ibrbine Stcp Valve <10% Valve Closure X (4) X (4) X (4) A&C tbtes: 1. There shall be two cperable or tripped trip system for each functicn.

2. Permissible to bjpass, with control rad block, for reactor protection systen resec in REWEL and SUIIXM positions of the reactor made switch.

3. Bypassed when reactor pressure is <600 psig.

4. Bypassed when first stage turbine pressure is less than that which uxt@d to s 45% rated staan flow (generator out[ut approximately 307 mb).

i 3/4 1-3

! Millstone - thit 1 Anenduent No. 98 -

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. 2. . ~- x. ~ . .. 2..m.w ,xx. w.m 4- . .c ..

5. IRH's are bypassed when made switch is placed in run. 'Ihe detector for each cperable IIM denel shall be fully imerted until the -lated APIN channel is cperable and indicatirg at least 3/125 full scale.****

6. The design pennits closure of any cne valve without a scram beiro inltiated. .

7 May be bypassed when reary by closing the mamal instrutent isolation valve for scram cf PS-1621 A throuth D irirg purging for ocntaintent inertito or &inerting.

8. When the reactor is subcritical ard the reactor water tarperature is less than 212 P, only the following trip functions need to be cperables

a. Mach Switch in Sutdown

b. mnual Scran

. c. High Flux IIM l d. Scran Discharge 1blute High Ievel

e. APfM Rechoed High Flux ,

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9. Not required to be cperable when primary contairnent integrity is not required. j t

10. With the node witch in "run position" an incperative trip fmetion also requires an associated APIM "&wnscale i i

alarm." I l  !

11.

Trip functicrs are rot recpired to be cperable if all ocntrol rods are fully inserted, and either electrically cr j hydraulically disanned in armrdance with Specification 4.1.D. '

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! *Acticn: If the first colutn canrot be met for cne of the trip systens, that trip systan shall be trigped. If the first colwn l

cannot be met for both trip systers, the a[ptrpriate acticrs listed belos shall be taken: .

A. Initiate inserticn of cperable rods and cr2rplete inserticn of all cperable reds wf. thin four hours.  :

B. Reduce power level to IIM range and pla made switch in the StartxWHct Stanty positicn within eight hours.

C.  !

Rxboe turbire load and close main stosn line isolatim valves within eight hours.

An APRM will be ocnsickred irrperable k there are less than two LPIM irputs per level or there are less than 50% cf the l norml canplinent of IFfM's to an APIN.

-l Om inch cn the water level imtrutentation is 127 atove the try of the active fuel.

Per errata sheet (hted 10-7-70.

I 3/4 1-4 Millstone - Unit I heen&ent No. JNI, 110 I

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SJRVEIIING P90lJIRDENT IJMrrifG CD0rnCN KR QU4ATICN -

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'4.10 REFIELDG NO SPENT ftEL IWELING

.10 DEFU[LDG NO S11NT [UL llANDLItG Aplicability:

[mliczdallity:

Applies to the periodic testirg of those interlocks and ,

Amlie's to fuel lar111rg, axo reactivity 11mitations, ard instrunents used dirirg refuelirg and spent fuel spent fool hanilito, handling.

I Cbjective Cbjective: i i

'Ib assure cxxu reactivity is within czpability of the control To verify the cperability of instrunentation and I rods, to prevent criticality ducirg refuelirg, and to assure intericx:ks used in refuelirg and spent fuel handlirg. _ g. g safe harxility of spent fuel casks.

Specificaticn:

specification:

A. Refueliro Interlocks A. refuelinct Interlocks Prior to any fuel hardlirg, with the head off the

! During cxxe alterations, the reactor acde switch shall be reactor vessel, the refuelirg interlocks shall be locked in the leuL positicn and tie refuelirg fmeticnally tested. 'Ihey shall also be teste$ at interlocks sin 11 be rperable, or all cxmtrol rods shall weekly intervals thereafter until ro langer inserted, arx1 either electrically or l

La fully required and follcwirg any repair work associated ly]ralically disaun.d. with the interlocks.  ;

If the refuelirg inter 1ccks are not cperable, all

centrol rods shall be verified to be fully inserted, and either electrically or hydraulically disarned in asuu.dmu.d with Specificaticn 4.1.D.

I Anendment No.,j[9,9d,110 Millstone - Unit 1 3/4 10.] .

f M r 6, 1985 LIMITIfC 0201 tim FOR GERMPIm SLRVEIUJNO: IEQUIRENNr B. Core Mcnitoriry B. Oore Monitoring Duriru core alteraticns tw> SEN's shall be cperab2e, one 1. Prict To nakirg any alterch' Ins to the core, in the core quadrant where fuel or ocotrol rods are beirg the GN's shall be functicnally tested and newed and one in an adjacent quairant, exc@t as specified checked for neutron respcrwe. Thereafter, the in Paragraphs 3 3nd 4 below. Ebr an SIM to be ocnsidered SRM's will be checked daily for response when cperable, the followirg crnditicns shall be satisfied: core alteraticos are beirg na&.

1. The SM shall be inserted to the normal cperatirg 2. Prior to @iral unloMing or reloading, the level. (Use cf special nrwable chnkirg type SRK's shall be fmeticnally tested. Prior to

&tectocs & rirg fuel leadirg or reajor: core spiral unloadirg, the SIM's should also be alteratiers in place of rrmnal detectors is checked fcr neutron response, permissible as Icog as the &tector is ocnnected into the nontal SIM circuit.)

2. The SIN shall have a minintun tw.atrm irdmi ocunt .

rate of three per second witt; all rods fully irserted in the core. ~a

3. Prior to unloadirg, the SIN's si.all be prmen operable as stated above, however, chrirg spiral unloadirg, the catnt rate nay drcp below 3 cys.

4. If required, special nrwele &nkirg type dew +m can be inserted into the cte, price to relcadirg fuel assablies into the central core regicn (with all ocntrol rods inserted). Before &he ninth fuel assa bly is IrwM into the core it. tin close proximity of the novable <inkirg chaiters or the SIN's, Paragraphs 3.10.B.1 and 2 agply.

Arendnent tb. fd,107 3/4 10-2

High radiation levek in the nain stemnlire tunnel atxwe that due to the rormal nitrogen and cuygen radioactivity is an indication of leakirg fuel. A scran is initiated whenever su& radiaticn level exr-k seven times nmaal backgrourd.

The purpose of the scran is to rukm the source of su& radiaticn to the extent rw-aary to prevent excessive rel-of radioactive materials. Discharge of ex ssive arounts of radioactivity to the site erwirons is prevented by the air ejector off-gas acnir ors which cause an isolaticn of the nain mndenser off-gas line provided the limit for a 15-mirute period specified in specificaticn 3.8 is rot exrwavi.**

The main steanline isolaticn valve closure scran is set to scran when the isolation valves are 10% clmed frun full open j in three out of four lines. This scran anticipates the presure and flux trarsient, which would emir when the valves close. By scranning at this setting the resultant transient is insignificant. Ibf. Secticn 11.3.7 FSAR.

A reactor made switch is provi&d which actuates or typasses the various scran fmetions qvuviate to the partimlar plant cperating status. Ref. Section 7.2 ESAR. l he manual scran functicn is active in all nois, thus providirg for a marual means of rapidly irserting control rot irirg all nodes of reactor cperation.

20 11+1 ard AFIN systan provich protection ajainst excessive power levels and short reactor periods in the refuel ard StartupAlot Stan&y unies. A scurce range ntnitor (SIM) systan is also provided to syply additicnal neutrcn level 3 information durity starttp tut has ro scran functions. Thus the IIM and APIM systans are required in the refuel ard )

StartupAlot Standby nods. In the power range the AMM provides the rapired protections; tius, the IIM systan is not required in the Ibn node.

The high reactor pr-re, high drywell pressure, reactor low water level, and scran discharge volune high level scrans are required for StarttpAbt Stan@y ard Pun no&s of plant cperaticn. %ey are, therefore, required to be cperational for these modes of reactor cperaticn.

%e recpirenent to have all scran functions except those listed in tbte 8 of Table 3.1.1 cperable in the Ibfuel ad j Shutdown node is to assure that shifting to the Refuel txxb &rirg reactor poder operation &es not diminish the need for the reactor protecticn systan. As indicated in Note 11 of Table 3.1.1, no trip functicns are ruquired to be cperable if all cxntrol rtds are fully inserted, ard either electrically or hydraulically disanred, since this prrditicn assures nnxinun negative reactivity insertion.

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• • Ebr errata sheet dated 10-7-70 B 3/4 1-3 Millstcre - Unit 1 Amendnent No.j$ Jg. ]l0

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The turbim cxnkwier low vacusa scram is cnly required dirirg ptwer coeration and nust be by[wwwwi to start up the unit. At low power cxnlitions a turbine stcp valve cimire does not result in a transient which milti not be handled i

safely by other scras such as the APIN.

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l The requiraient that the IIN's be irserted in the cxxe when the APIM's read 3/125 cr 1cuer of full smle maaires that ,

there is pttver overlap in the neutron nmitoring ytais ard thm, that arhyate coverage is prwided for all ranges of I' j

reactor cperation. l I

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B 3/4 1-4

.. m - _ , _ n .. i pr ,n w w . m . g

3.10 Bases A. Refueliro Interlocks During refuelirg cperatims, the reactivity potential of the axe is being altered. lt is rw=siary to regaire certain interlocks and restrict certain refueling prmartires asch that there is aamrance that inadvertent critality &es not occur.

To minimize the possibility of loading fuel into a cell cmtaining no etntrol rod, it is required that all cxmtrol rods are fully inserted den fuel is being lewiari into the reactor core. 'Ihis requirement maseires that &rirg refueling the refueling interlocks, as deskred, will prevent inadvertent criticality. 'Ihe core reactivity limitaticn d 3 Specificaticn 3.2 limits the core alteratims to maseire that the resulting crxe Irwiirg can be etntrn11ari with the reactivity control systen and interlocks at any tine &rirg stat &wn er the followirg operating cycle.

Ackliticn of large annts cf reactivity to the cxxe is prevented by cperating prorwtires, diich are in turn backed to by refueling interlocks cn red withdrawal and movement of the refuelirg platfcon. Men the node switch is in the IEREL positicn, inter 1cris prevent the refuelirg platform fran being noved over the core if a control rod is withdrasn and fuel is cn a hoist. Likewise, W the refuelirg platfoon is over the core with the fuel on a hoist, control rod noticn i is blocked by the interlocks. With the node switd1 in tle IUUEL positicn, cnly one (Introl red can be withdrawn.

With all otntrol rods fully inserted, and either electrically cr hydraulically dier=vi, ner.inun negativs teactivity inserticn is == ired, therefore, the reftelirg interlocks are not regaired to te qxt 61e.

Ebr a new cate, the dzqpiry of a fuel assenbly into a vacant fuel location adjacent to a withdrawn crmtrol red does not j result in an excursion or a critical conficy2raticn, thus, =bgnte nargin is provided.

B. Core Manitoriru .

The SIN's are provided to nonittr the core & ring periais of station stut&wn aru3 to guide the ci-%x &rirg refueling operations and station startip. Recpiring two cperable SIN's, one in and cne adjacent to any core cpadrant dare fuel or crntrol rcxh are being noved masaires whgiate monitority of that quadrant &rirg such alteraticns. The rocpirement cf three neutrxn irrhrwi count per seccnd provide wun ance that reutron flux is beirg mcnitored.

i j During unloadirg, it is not rwmary to naintain 3 cos harmaa core alterations will involve cnly reactivity removal arx1 will not result in criticality.

B 3/4 10-1 i Millstcne - Unit 1 Amenchent tb. #f. M. 110

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l During the loadirg of an eipty sourceless core, the special mwable dr*irg type fission detectors will not detect a r Therefore, fuel nust be planari in the core to establish a neutron neutron count Wa==a of the lack of neutrtn sources. l count rate.

The restriction of eight fuel assenblies will minimize the prtbebility of an inadvertent criticality pricr  ;

to achievirg 3 cps, while providing the flexibility to load fuel bundles around the portable detectors and SIM's.

Ip, C. Ebel Storage Pbol Mter Level

'To assure that there is adequate water to shield and cool the irradiated fuel M11es stored in the be it would pool, a ndnima a signifimnt.

pool water level is established. The mininun water level of 33 feet is established ben ===a change frun the normal level (37' 9"), well above a level to assure adeqiate cooling (just above active fuel).

D. Crane Operability 1 The cperability requirunents of the crane used for handlirg of spent fuel casks ensures that the redindant features of the crane have been aanrptely irugw+ari. The redandant hoist systan ensures that a load will not be &g for all

• postulated credible sirgle-etmpcrient failures. '

I E. Crane Travel

'Ihe restricticn of novenent of spent fuel casks over irradiated fuel ensures (in adfition to the rushndancy features) F that a cask camot be cktpped cn irradiated fuel Miles.

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l B 3/410-2 n m aert m,on

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