ML18011A878

Proposed Tech Specs,Revising Various Portions of Section 3/4.9, Refueling Operations to Be Consistent w/NUREG-1431, New Std TS for Westinghouse Plants & Relocating Applicable Sections Per Commission Final Policy Statement

ML18011A878
Person / Time
Site:	Harris
Issue date:	04/05/1995
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18011A877	List: ML18011A875 ML18011A878
References
RTR-NUREG-1431 NUDOCS 9504110051
Download: ML18011A878 (31)

Text

ENCLOSURE TO SERIAL: HNP-95-024 ENCLOSURE 5 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO, 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT REFUELING OPERATIONS c

PDR P

ADOCK

'DR 95041i005l 950405 05000400 E5-1

C s> ~

~

LIMITZNC CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3/4.8o4 TABLE TABLE 3/4.9 3/4 9

~

TABLE

~

3/4.9.2 3/4.9.3 3/4.9.4 3/4.9.5 3/4.9.6 3/4.9.7 3/4.9.8 3/4.9 '

3/4.9o10 3/4.F 3/4.9 1

3.9-1 11 12 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES 3.8-1 DELETED..

BORON CONCENTRATION REFUELING' H xghh

~ ~ ~ ~

Water Level. ~

Los Water 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARCINo

... ~

1 os Containment Penetration Conductor Overcurrent INSTRUMENTATION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

( TIELETED)

CONTAINMENT BUILDING PENETRATIONS DELE>EO C ~GLEYED)

~ ~

,...,,,

Motor-Operated Valves Thermal Overload 3.8"2 DELETED ~ ~ ~ ~ ~ ~ ~ . ~ ...... ~ . ~ .

REFUELINC OPERATIONS

'

INDEX Protective Devxcesooo.oooooo'o.oooooo.ooo..o.ooooo..o.oo

~ ,, ~ .. ~

~ ~ ~

~ ~ ~ ~ ~ ~ ~

ADMINISTRATIVE CONTROLS TO PREVENT DILUTION DURINC

.~~o~~o

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

RESIDUAL HEAT REMOVAL'AND COOLANT CIRCULATION

............ ...

Level...................

CONTAINMENT VENTILATION ISOLATION SYSTEM.

WATER LEVEL -

WATER LEVEL -

REACTOR VESSEL.

NEW AND SPENT FUEL POOLS FUEL HANDLING BUILDING EMERCENCY EXHAUST SYSTEM.

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3/4.10.2 CROUP HEIGHT~ INSERTIONs AND POWER DISTRIBUTION LIMITS' ~

~

'

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~

...,......,,...,.....,.

.o

~

".

..

~ ~ ~ ~

~

~

Protection........

.o. .. .. . ....

~ ~ ~ ~ ~ ~ ~ ~

~ ~

os

i

.................

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

. ~ .. ...

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3/4.10.3 P HYSICS TESTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~

3/4,10.4 REACTOR COOLANT L'OOPS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWNo ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~

~

~ ~

~ ~ ~

~ ~ ~

~

3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 PACE 8-19 8-21 8-39 8-40 3/4 9"1 3/4 9-2 3/4 9"3 uo s-(

3/4 3/4 3/4 9-5 9-6 9-7 9-8 9-9 9-10 9-11 9-12 9-13 9-14 10-1 10-2 10-3 10-4 10"5 SHEARON HARRIS - UNIT 1'1 Amendment No. )'3, ~

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4. 7, 1 TURBINE CYCLE. 8 3/4 7-1 3/4o7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION........ 8 3/4 7-2 3/4.7. 3 COMPONENT COOLING WATER SYSTEM.. 8 3/4 7-3 3/4.7.4 EMERGENCY SERVICE WATER SYSTEM. 8 3/4 7-3 3/4. 7. 5 ULTIMATE HEAT SINK.......... 8 3/4 7-3 3/4.7. 6 CONTROL ROOM EMERGENCY FILTRATION SYSTEH............... 8 3/4 7-3 3/4.7. 7 REACTOR AUXILIARY BUILDING EMERGENCY EXHAUST SYSTEM.... 8 3/4 7-3 3/4. 7 8

~ S NUBBERS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ 8 3/4 7-4 3/4. 7. 9 SEALEO SOURCE CONTAMINATION............................ 8 3/4 7-5 3/4. 7. 10 ( DELETED ) ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 7-6 3/4.7.11 ( DELETED) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ 8 3/4 7-6 3/4.7.12 AREA TEMPERATURE HONITORING............................ 8 3/4 7-6 3/4 7.13 ESSENTIAL SERVICES CHILLEO WATER SYSTEM................ 8 3/4 7-6 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, ANO 3/4.8.3 A.C. SOURCES, O.C. SOURCES, ANO ONSITE POWER DISTRIBUTION................ - .. -........ 8 3/4 8"1 3/4.8. 4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES................ 8 3/4 8-3 3/4. 9 REFUELING OPERATIONS 3/4. 9. 1 BORON CONCENTRATION............................. ~ ~ . 8 3/4 9-1 3/4.9. 2 INSTRUMENTATION......................--............ 8 3/4 9-1 3/4. 9. 3 ( ~~L T@)o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 3/4 9-1 I 3/4. 9. 4 . CONTAINMENT BUILDING PENETRATIONS......,, 8 3/4 9-1

9. 5 (.DK4<~<<) ............................ . 8 3/4 9-1 (v'/4.

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

3/4.9.6 (Qe,~~ra~).....,................................ 8 3/4 9"2 3/4o9o7 (QE<FTK) ii o ~ ao o o ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 9"2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION..... ~ 8 3/4 9"2 3/4. 9. 9 CONTAINMENT VENTILATION ISOLATION SYSTEM........... 8 3/4 9-2 3/4.9. 10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL ANO NEW ANO SPENT FUEL POOLS oo ~ ~ ~ ~ ~ ~ ~ 8 3/4 9-3 3/4.9.12 FUEL HANDLING BUILDING EHERGENCY EXHAUST SYSTEM.... 8 3/4 9-3 SHEARON HARRIS - UNIT 1 XV

4 DEFI NITIONS CONTA'INMENT INTEGRITY L:7 CONTAINMEVT INTEGRITY shall exist when:

a ~ A'll penerracions required co be closed during accidenc conditions are either:

1. Capable ot being closed by an OPERABLE concainmenc aucomacic isolation valve system, or

2. Closed by manual valves, blind fLanges, or deaccivated aucomacic valves secured in their closed positions, except as provided in Speciticacion 3.6.3.

b. All equipment. hatches are closed and sealed,

c. Each air lock is in compliance sich che requirements ot'pecificacion 3.6.1.3,

d. The containmenc leakage races are Mithin che limits of Specificacion 3.6.1.2, and e . The sealing mechanism associared Mith each penetration (e.g., Maids, belloMs, or 0" rings) is OPERABLE.

CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be chat seal Mater floM supplied Lo the reactor coolant pump seals. 1.

CORE ALTERATION 1.9 CORE TERATI sha 1 be th moveme c or nipuL ion oc any co ponen Mic in ch reacco ptes ure ves 1 vith che v seL he d remov d and fuel ch vess . Sus nsio of COR ALTERA ION s ll not preclud comp etion f vemenc of a c ponent to a s fe con ervarive posi ion.

CORE OPERATINC LIHITS REPORT 1.9.a The CORE OPERATINC LINITS REPORT is che unit-specific documenc that provides core operacing limits for the current operating reload cycle. These cycle-specific core operating Limits shall be determined for each reload cycle in accordanc'e Mith Speci'fication 6.9.1.6 . PLanc operation Michin these core operacing Limits is addressed Mithin che individual specifications, DICITAL CHANNEL OPERATIONAL TEST 1.10 A DIGITAL CHANNEL OPERATIONAL TEST shall consist o! exercising che digi" cal compucet hardMare using data base manipulation to verify OPERABILITY of alarm and/or tr'ions.

L9 CORE ALTERATlel shall be the covenant of any fuel, sources, reactfvlty control coeponents, or other conponents affecttnS reactivity>>ithunn the reactor vessel >>1th the vessel head remved and fuel ln the vessel. Suspension of CORE ALTERATIORS shall Amendment No.

not preclude conpletlon of covenant of a conponent to a safe posltlon.

ON ant the rc4 I'~ ~P ~$ (4lpl +ho Llhblt'p~fjg /A g4, gg? p 3.9,1.a S

ens stem ~ The box'on concentration of all filled portions of the Reactor Coolant the refuelin canal shall be maintained uniform an s more rest ctive o e o ov react v condit ons is met either:

1) A bor n concen ation to intain xx less or eq to 0.95 as spec fied in e COIL, (2) A oron con ntration f greate than or e 1 to 20 0 ppm.

3.9.l.b The valves listed in Table 3.9-1 shall be in their positions required by Table 3.9-1.

1C&UIJIX MODE 6.

MGQH:

go)'>ops 4o rwQA?. }Sf'on li~'ks>>

Cubic&~)~ *

a. Qith the requirements f Specification 3.9.1.a not satisfied, iaaediately suspend all operatio involvi CORE hLTEBATIONS or ositive reactivi c <

b. An ANALOC 4 OPERATIONAL TE vithin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rior o the initia start o ORE ALTERATIONS, nd

c. An ANALOC 0 TION TEST at east on per days.

P >~>NC.< gP~GA&TZ(ll% one P4~ I'8 ~n hS SHEARON HARRIS - UNIT 1 3/4 9-3 Amendment No.

'f GRUELING OPERATIONS 3/4.9.3 ECAY TIME - bGLETE LIMITING CONOITI OR RA 3.9.3 The rea r shall ubcritical for at least ours.

PLICA ITY: Ouring movement o radiated f fn the reac vessel.

0.

Nth the re tor subcritical for ss than 10 urs, suspend all o at s involving mov nt of irradi d fuel in the reac vessel.

SURVEILLANCE RE U 4.9.3 reactor shall be ermined to have b subcritical for least 100 rs by verification of th ate and tim of subcriticality prio~

ement of irradiated fuel in the actor essel.

SHEARON HARRIS - UNIT 1 3/4 9-4

REFUELING OPERATIONS 3/4. 9. 4 CONTAINMENT 8UILQ ING PENETRATIONS LIMITING CONOITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:

a. The equipment door closed and held in place by a minimum of four bol ts,

b. A minimum of one door in each airlock is closed, and Cr Each penetration providing dfrect access from the containment atmosphere to the outside atmosphere shall be either:

0, manual nr

1. Closed by s i va nd or QVPOM04I < , ma v or isolation wfvg 5fI'nd fiaqe ITr

2. He capable of being closed by OPERABLE automatfc normal contain-ment purge and containment pre-entry purge makeup and exhaust equi'lumni) or isolation valves.

APPLICABILITY: Ouring CORE ALTERATIONS or movement of irradiated fuel within ACTION:

Nth the requfrements of the above speci ffcatfon not satfsffed, ftmaediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel fn the containment buf]ding.

SURVEILLANCE RE UIREMENTS 4.9.4 Each of the above required containment buildfng penetrations shall be determined to be either fn fts closed/isolated condition or capable of being closed by OPERABLE autoaatfc normal containment purge and containment pre-entry purge ma up and exhaust, isolation valves u ro 5 at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel fh the containment building by:

a. Verffyfng the penetrations are in their closed/isolated condition, or

b. Testing the normal containment purge and containment pre-entry purge makeup and exhaust fsolatfon valves per the applicable portions of Specification 4.6.3.2.

SHEARON HARRIS - UNIT 1 3/4 9-5

EF'UELIN OPERATIONS 3/4.9. COMMUNICATIONS - yggg~y LIMITING CONO N FOR OPE ON 3.9.5 Ofrect coae fons shall be maintained batw the control roo nd personnel at t refuelfn tatfon fn co'ntafnaent.

APPLICAB: Ouring CORE AL TIONS.

A N:

When direct coaeunfcatfons be n the cont roea an ersonnel at the refueling station cannot be ntafned, suspen l E ALTERATIONS.

SURVEILLANCE RE UI ENTS 4.9.5 Oir coeaunfcatfons between control rooa and person at the retceli station in contafnment sh be deaonstrated within 1 hou rior to the art oi'nd at least once p 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.

SHEARON HARRIS - UNIT X 3/4 9-6

FUELING OPERATIONS 3/4.0.6 REFUELING MACHINE - QELE~b L M 3.9.6 The r uelfng machfn and auxflfary. hoist shall be used fr movement of drive rods or el assembl es and shall.he OPERABLE with:

a. The ref lfn machfne, used for movement of fuel semblies, having:

1. A af capacity of 4000 pounds, and automa c overload cutoff lfaft le than or equal to 2700 ounds.

b. auxflfarJJ hofs used fot latching d unlatching drive rods, avfng:

l. A minimum capacity f 3000 p ds, and

2. A 1000-pound load fnd a that shall be used to monitor loads to prevent lifting more an 600 pounds.

APPLICABILITY: Ouring movement of ve s or fuel assemblies wfthin the reactor vessel.

ACTION:

,fifth the requirements for th refueling machine or auxiliary st OPERA-BILITY not satisfied, susp use of any inoperable fueling fne and/or auxiliary hoist from oper fons involving the mov of drfv rods and fuel assemblies wfthfn the r vessel.

SURVEILLANCE RE UI ENTS 4.9.6.1 The uelfng machine used for movement o fuel assemb s withfn the reactor v sel shall be demonstrated OPERAS, within MO hou prior to the start o such operations, by performing a test of at least 0

. pounds . nstratfng an automatic load ff at less than or eq 1 to 2700 po 4.9.6 The auxflfary hoist and associ load fndfcator used for mov t of fve rods within the reactor vess shall he demonstrated OPERABLE with 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> prior to the start of s operations by performing a load test of ast 900 pounds.

SHEARON HARRIS - UNIT 1 3/4 9-7

RXFjELING OPERATIONS 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING - DEI-~><>

LIMITING CON N FOR OP 3.9.7 Loads in exce of 2300 pounds shall be prohibited travel over

-fuel asseeblies i e rage pool.

APPLICABILI . With irradia fuel assemblies storage pool.

ACTIO '

a. Nth the requireaents of ve specification not satisfi, place the crane load in a sa conditi

b. The provisions o peciffcations 3.0.3 d 3.0.4 ar not applicable.

SURVEILLANCE RE U 4.9.7 Cr interlocks and physical stops ~ prevent crane t el with loads excess of 2300 pounds over fuel emblies shall be deaons ted OPE within 7 days prior to crane and at least once per 7 day t reafter during crane operation.

SHMON HANlS - UNIT 1 3/4 9-B

REFUELING OPERA S 3/4.9. 10 WATER L EL - REACTOR VESSEL LIHITING CONOITXON FOR OPERATION 3.9.10 't least 23 feet of water shall reactor vessel flange.

be caintained over the top of the APPLICABILITY: HOOK 6, du in voce of f el as enbl es or contro rods e con > w n e er fuel ass ies ting ved,o the fuel ss lie se ed w thin e actor vesse are ad ted.

ACTION:

Nth the r uirenents of e ov iff ion n t satisfied sus end ll op at o nvolvi mov nt fu ass~lies r con rol ds th th n

ctor essel or 'ntai nt af r placing ass li in rans in s e

+fit n).

SURVEILLANCE REOUIREHENTS 4.9.10 The water level shall be deterained to be at le ts ainiean required depth once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

~~~'~~q~~+ < >rgaktakL 4 sl ass~blies <fW n combine n$ a~

~ Al:TBMTsoHS, &(cop/ der)lp IR44~ng ul~y N c~i rJ. k>~ she.

Z ASc& ~

QOQE ALTB @~ON< y

>Mlltfiwq Opia A>>M lndOIVihp OCUC I%~ Pf

~ss~ll' ulkvin md%:hmeik a4 lni(iwtg. aplong +y

~<@ra ec4slip c,aully u)a4'm to u/ 0'hin lim'Q SHKANN HARRIS - UNIT 1 3/4 9 I2

BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that: (1) the reacto~ will remain subcritical du~ing CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety anal-yses a ue . r ess or ff nc u es a pcm con erva s e a ow n or u ert in es. milar y, the oron onc ntration value f 00 r r ter inc udes cons vative uncer int allowan of oro . The administrative controls over the required va ves during re ue >ng operations precludes the possibility of uncontrolled boron dilution of the filled portion of the RCS. This action prevents flow to the RCS of unborated water by closing flow paths from sources of unborated water.

3/4. 9. 2 INSTRUMENTATION ~y-8, ~

gp~<QQ lg 44 QdC 5PCCff7c, Co~e The OPERABILITY'of the Source Range Neutron Flux Monitors ensures that redun-dant,monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 OECAY TIME-~F~pg The minimum require ent for r actor sub iticali prior o movemen of irradiated fuel as emblies i the reac r vessel ensures hat suff cient ti e has elapsed to al ow the ra ioactive cay of e short- ived fis ion prod cts Thi deca time s consisQnt with t assumpt ons used in the s ety ana yses 3/4.9. 4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be re-stricted from leakage to the environment. The OPERABILITY and closure restric-tions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

3/4.9. 5 COMMUNICATIONS <<>g~~

The oui i personnel nt for co unicationgcapahil/ty containme t.can be promptly j'nformed ensu f

s that n i'ueling station signif cant changes in the 'facili y status o core reac4ivit cohditions durin C E ALTERA7IONS.

SHEARON HARRIS - UNIT 1 8 3/4 9-1

REFUELING OPERATIONS BASES 3/4 9.6 REFUELING MACHINE uirement for th refuel ng ma ine enquire th 5: (1) efuel-The ERABILI ing chine (2) each cra illhare e

Y b used suffici fo nt moveme loa t of d ive "ro s and K6eL ass mblies, capaci y to ft a drive rod or fue as embly, a d (3) the cor intern Ls and react vesseLI are pr tected from e cessive iftin force n the e ent th y are nnadvertently e gaged~during lj.fting o rati s. / /

3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING ~ g)ggP~b The r stricti n on'ov ent o loads n exces of t e nom'nal we ght jf a fuel and ontrol od a semb and ssoci ed hand ing t 1 ov oth fuelf assemblies in e stor ge p ol e ures hat i the ev t thi load xs dr9 ped:j(1) the ac vity r leas wil be 1'ted that ntain d in single fuelI assembly, a (2) apy posaihi dissolution f fuel oritioal array.

'he terat raohs will mot result n is ssuept'on is o sist t wit the aotivi y release

~

ssumed .xn tQ saf ty a alyses I

I 3/4e9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION s

The requirement that at least one residual heat removal (RHR) loop be in opera-tion ensures that: (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.

The requirement to have two RHR loops OPERABLE when there is Less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and at least 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR Loop, adequate time is provided to initiate emergency procedures to cool the core.

The minimum RHR flow requirement is reduced to 900 gpm when the reactor ~ater leveL is below the reactor vessel flange. The 90d gpm limit reduces the possibility of cavitation during operation of the RHR pumps and ensures sufficient mixing in the event of a MODE 6 boron dilution incident.

3/4 9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge makeup and exhaust penetrations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

SHEARON HARRIS - UNIT 1 B 3/4 9-2 Amendment No. ~

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices. .. . 3/4 8-19 TABLE 3,8-1 DELETED. 3/4 8-21 Motor-Operated Valves Thermal Over load Protection....... 3/4 8-39 TABLE 3.8-2 DELETED. 3/4 8-40 3/4. 9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION. 3/4 9-1 TABLE 3.9-1 ADMINISTRATIVE CONTROLS TO PREVENT DILUTION DURING REFUELING. 3/4 9-2 3/4.9.2 INSTRUMENTATION........... 3/4 9-3 3/4.9.3 (DELETED). 3/4 9-4 I 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS .. 3/4 9-5 3/4.9.5 (DELETED) 3/4 9-6 3/4,9.6 . (DELETED)o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 9-7 3/4.9.7 (DELETED)..... ~ ......... ....... ~ 3/4 9-8 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level. . 3/4 9-9 Low Water Level 3/4 9-10 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM...... 3/4 9-11 3/4.9.10 WATER LEVEL - REACTOR VESSEL . ......... . ... 3/4 9-12 3/4.9.11 WATER LEVEL - NEW AND SPENT FUEL POOLS... 3/4 9-13 3/4.9.12 'FUEL HANDLING BUILDING EMERGENCY EXHAUST SYSTEM,........ 3/4 9-14 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN............... 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS.. 3/4 10-2 3/4. 10. 3 PHYSICS TESTS ~... .. ~ 3/4 10-3 3/4. 10.4 REACTOR COOLANT LOOPS..... 3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN.. 3/4 10-5 SHEARON HARRIS - UNIT 1 X1 Amendment No.

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7. 1 TURBINE CYCLE.................. B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION.......... B 3/4 7-2 3/4.7.3 COMPONENT COOLING WATER SYSTEM................... B 3/4 7-3 3/4.7.4 EMERGENCY SERVICE WATER SYSTEH. B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK. B 3/4 7-3 3/4.7 ' CONTROL ROOM EMERGENCY FILTRATION SYSTEM.. 8 3/4 7-3 3/4.7.7 REACTOR AUXILIARY BUILDING EMERGENCY EXHAUST SYSTEM...... B 3/4 7-3 3/4.7.8 SNUBBERS B 3/4 7-4 3/4.7.9 SEALED SOURCE CONTAMINATION. B 3/4 7-5 3/4.7.10 (DELETED). B 3/4 7-6 3/4 '.11 (DELETED). B 3/4 7-6 3/4.7.12 AREA TEMPERATURE MONITORING. B 3/4 7-6 3/4 7.13 ESSENTIAL SERVICES CHILLED WATER SYSTEM. B 3/4 7-6 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, AND 3/4.8.3 A.C.

ONSITE POWER SOURCES, DISTRIBUTION..... '...........

D.C. SOURCES, AND 8 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...... B 3/4 8-3 3/4. 9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION..............,.. B 3/4 9-1 3/4.9.2 INSTRUMENTATION. B 3/4 9-1 3/4.9.3 (DELETED). B 3/4 9-1 I 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS B 3/4 9-1 3/4.9.5 (DELETED).. B 3/4 9-1 3/4.9.6 (DELETED).. B 3/4 9'-2 3/4.9.7 (DELETED).. B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION........:... B 3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM ............. B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND NEW AND SPENT FUEL POOLS .. B 3/4 9-3 3/4.9.12 FUEL HANDLING BUILDING EMERGENCY EXHAUST SYSTEM......... B 3/4 9-3 SHEARON HARRIS - UNIT 1 XV Amendment No.

II 1

DEFINITIONS CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:

a. All penetrations required to be closed during accident conditions are either:

1. Capable of being closed by an OPERABLE containment automatic isolation valve system, or

2. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Specification 3.6.3.

b. All equipment hatches are closed and sealed,

c. Each air lock is in compliance with the requirements of Specification 3.6.1.3,

d. The containment leakage rates are within the limits of Specification 3.6. 1.2, and

e. The sealing mechanism associated with each penetration (e.g.,

welds, bellows, or 0-rings) is OPERABLE.

CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.

CORE ALTERATION 1.9 CORE ALTERATION shall be the movement of any fuel, sources, reactivity control components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS REPORT 1.9.a The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits 'for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.6. Plant operation within these core operating limits is addressed within the individual specifications.

DIGITAL CHANNEL OPERATIONAL TEST 1.10 A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation to verify OPERABILITY of alarm and/or trip functions.

SHEARON HARRIS - UNIT 1 1-2 Amendment No.

f 3/4.9 REFUELING OP IONS 3/4.9. 1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1.a The boron concentration of all filled portions of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained and within the limit specified in the COLR. 'niform 3.9.1.b The valves listed in Table 3.9-1 shall be in their positions required by Table 3.9-1.

APPLICABILITY: MODE 6.

ACTION:

a. With the requirements of Specification 3.9.1.a not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes, and initiate actions to restore boron concentration to within limits.

b. With the requirements of Specification 3.9.1.b not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes, and initiate action to return the valve(s) to the position required by Table 3.9-1.

SURVEILLANCE REQUIREMENTS 4.9.1.1 The boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be determined by chemical analysis to be within the limits of the COLR at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

4.9.1.2 At least once per 31 days, verify that the valves listed in Table 3.9-1 are in their positions required by Table 3.9-1.

SHEARON HARRIS - UNIT 1 3/4 9-1 Amendment No.

REFUELING OPERATIO 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE, each with continuous visual indication in the control room and one with audible indication in the containment and control room.

APPLICABILITY: MODE 6.

ACTION:

a. With one of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes'ith both of the above required monitors inoperable or not operating, in addition to Action a. above, immediately initiate actions to restore one source range neutron flux monitor to OPERABLE status and determine the boron concentration of the Reactor Coolant System within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

SURVEILLANCE REQUIREMENTS 4.9.2 Each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:

a. A CHANNEL CHECK at least once per 12 hours,

b. A CHANNEL CALIBRATION once per 18 months.

SHEARON HARRIS - UNIT 1 3/4 9-3 Amendment No.

REFUELING OPERATION 3/4.9.3 DECAY TINE - DELETED SHEARON HARRIS - UNIT 1 3/4 9-4 Amendment No.

~

y~

c) . REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION F'R OPERATION 3.9.4 The containment building penetrations shall be in the following status:

a. The equipment door closed and held in place by a minimum of four bolts,

b. A minimum of one door in each airlock is closed, and

c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:

1. Closed by a manual or automatic isolation valve, blind flange or equivalent, or

2. Be capable of being closed by OPERABLE automatic normal

'ontainment purge and containment pre-entry purge makeup and exhaust isolation valves.

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.

SURVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its closed/isolated condition or capable of being closed by OPERABLE automatic normal .containment purge and containment pre-entry purge makeup and, exhaust isolation valves at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by:

a. Verifying the penetrations are in their closed/isolated condition, or

b. Testing the normal containment purge and containment pre-entry purge makeup and exhaust isolation valves per the applicable portions of Specification 4.6.3.2.

SHEARON HARRIS - UNIT 1 3/4 9-5 Amendment No.

REFUELING OPERATION 3/4.9.5 COMMUNICATIONS - DELETED SHEARON HARRIS - UNIT 1 3/4 9-6 Amendment No.

i, >

REFUELING OPERATION 3/4.9.6 REFUELING MACHINE - DELETED SHEARON HARRIS - UNIT 1 3/4 9-7 Amendment No.

(q, REFUELING OPERATIONS e 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING - DELETED SHEARON HARRIS - UNIT 1 3/4 9-8 Amendment No.

REFUELING OPERATION 3/4.9. 10 WATER LEVEL - REACTOR VESSEL LIMITING CONDITION FOR OPERATION 3.9. 10 At least 23 feet of water shall be maintained. over the top of the reactor vessel flange.

APPLICABILITY: MODE 6, during movement of irradiated fuel assemblies within containment, or during CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts.

ACTION:

With the requirements of the above specification not satisfied, suspend CORE ALTERATIONS, including operations involving movement of fuel assemblies within containment, and initiate actions to restore refueling cavity water level to within limits.

SURVEILLANCE REQUIREMENTS 4.9.10 The water level shall be determined to be at least its minimum required depth once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SHEARON HARRIS - UNIT 1 3/4 9-12 Amendment No.

3/4.9 REFUELING OP ONS BASES 3/4.9. 1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:

(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety analyses and are specified in the cycle-specific COLR. The administrative controls over the required valves during refueling operations precludes the possibility of uncontrolled boron dilution of the filled portion of the RCS. This action prevents flow to the RCS of unbor ated water by closing flow paths from sources of unborated water.

3/4.9.2 INSTRUMENTATION The OPERABILITY of the Source Range Neutron Flux Monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 DECAY TIME - DELETED 3/4.9. 4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

3/4.9.5 COMMUNICATIONS - DELETED SHEARON HARRIS - UNIT 1 B 3/4 9-1 Amendment No.

REFUELING OPERATION BASES 3/4.9.6 REFUELING MACHINE - DELETED 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING - DELETED 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION C

I The requirement that at least one residual heat removal (RHR) loop be in operation ensures that: (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron'dilution incident and prevent boron stratification.

The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and at least 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cool.ing. Thus, in the event of a failure of'he operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.

The minimum RHR flow requirement is reduced to 900 gpm when the reactor water level is below the reactor vessel flange. The 900 gpm limit reduces the possibility of cavitation during oper ation of the RHR pumps and ensures sufficient mixing in the event of a MODE 6 boron dilution incident.

3/4.9. 9 CONTAINMENT VENTILATION ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge makeup and exhaust penetr ations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

SHEARON HARRIS - UNIT 1 B 3/4 9-2 Amendment No.