Text

Suppl to Proposed Tech Spec Change 19,deleting Requirements Re Part Length Rods,Providing Overpressure Protection & Eliminating Inconsistencies Between Units 1 & 2 Tech Specs
	ML19256E007
Person / Time
Site:	North Anna
Issue date:	10/23/1979
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML19256E004	List: ML19256E003; ML19256E007;
References
	NUDOCS 7910250285
	Download: ML19256E007 (39)
	v • d • e

e 3 NORTH A?JNA UNIT NO. 1 SUPPLEMENT TO PROPOSED TECHNICAL PECIFICATION CHANGE NO 19 1210 227 g q 'S

'N 7910250

SUPPLEMENT TO ATTACHMENT A Evaluation of necessary changes to Unit ! Technical Specifit .tions as identified by page number.

Page 1-3, Index l i li Part length rod specifications should be deleted Page 3/4 1-11< Update the operability requirements for the reactivity 1-12^ control system charging pumps.

Page 3/4 2-3* Part length rod specifications should be deleted 2-76 2-12*

2-136 Page 3/4 4-5^ Revise the specification for startup of an isolated reactor coolant loop.

Page 3/4 4-266 Reactor vessel niaterial irradiation surveillance schedule needs revision to reference Appendix H.

Page 3/4 4-276 Update figures for heatup and cooldown curves to agree 4-28^ with figures previously submitted as part of the over-pressure protection review. Additionally, the update figures include a background grid.

Page 3/4 4-29* Delete the reactor vessel material irradiation surveillance schedule.

Page 3/4 4-30a e Add a new overpressure protec+. ion specification and basis 4-30b^ for unit which is similar to Unit 2 except for setpoints and no dependence upon pressurizer bubble for protection.

Page 3/4 5-66 Update the operabili ty requi rements for emergency core cooling system pumps.

Page 3/4 7-21 The specification for control room habitability systems should be made consi stent wi th proposed Uni t 2 requirements since the control room i s a common area.

Page 3/4 7-24 Update the specification for the safeguards area ventilation 7-25 system to be consistent with proposed Unit 2 requirements.

Page 3/4 10-5* Update the control rod position indicator channels surveillance requirements to be consistent with proposed Unit 2 requirements.

Page B 3/4 1-36 Update the specification for pH of containment sump water after a LOCA to reflect response to IE Bulletin 77-04.

) )_ \

_2-Page 8 3/4 2-1f Part length rod specifications should be cht.nged 2- 4 f:

Page B 3/4 4-il* Add a new basis for overpressure protection similar to Unit 2.

Page 5-44 Part length rods as a design feature should agree with Unit 2.

Page 3/4 3-106 Update the overtemperature aT specification to be con-sistent with proposed Unit 2 requirements.

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SAFETY EVALUATION At tached are the supplemental changes to the previously submi tted Technical Speci fica-tion Change No. i9 These changes consist of additional editorial corrections, dele-tion of addi tional references to part length control rods, changes to specifications for an isolated reactor coolant loop, and changes i ncor po ra ted in the overpressure protection specifications.

The specification changes for the control room habitability requirements are revisions to Regulatory Guide references, some of which were overlooked in the previously approved TSC No. 19 submittal.

Since the part length control rods are being removed during the upcoming refueling, additional references to these part length rods which were overlooked in the original submittal are now being deleted.

The change to the basis for Specification 3/4 1.2 reflects the response to !E Bulletin 77-04, dated 12-23-77, which deals with the pH of containment sump water following a LOCA.

The overpressurization protection system surveillance specification has been revised to reflect a Staf f comment during recent telephone conversations with the Staff regarding Unit 2. In addition, it has now been determined that the ability to use the pressurizer bubble for overpressure protection aill not be necessary for Unit 1.

The limiting condition for operation has been revised accordingly. The modifications will contribute to additior.al assurance of overpressure protection, in accordance with NRC Staff requirements.

Existing Technical Specification 3.4.1.3 requires that certain interlocks be satisfied and tnat a specific shutdown margin be maintained prior to opening the loop cold leg stop valve of an isolated loop. This currently applies in all modes. This requirement is overly conservative when applied to Modes 5 and 6. In addition, returning an isolated loop to operation in Mode 5 or 6 in accordance with this specification is not considered satisfactory. The isolated loop is not adequately vented, possibly affecting pump performance and operation.

The required interlocks prevent a " cold water" addition. and the minimum specified shutdown margin prevents an approach to criticality.

Filling an isolated loop is accomplished by utilizing the CVCS fill header. The source of water can be the RWST (2000 to 2l00 ppm of boron) or the Boric Acid Storage Tank to the Blender (the blender set to the requi red shutdown boron concentration) . If the RWST is utilized as the makeup source, its concentration is known and controlled by Technical Specifications. If the blender is used, the operator will use proven empirical nomographs to set the blender for makeup at the required shutdown boron concentration. Thus the shutdown margin is maintained under control.

With respect to " cold water" addition, the worst case reactivity change results in a change of 500 to 900 pcm or approximately 0.5 to 0 9% Ak/k. In Mode 6, 0.95 k eff 2000 ppm boron is required, whichever is more conservative. In Mode 5, k must be eff

<0.99 with a shutcown margin of >l.77% Ak/k required. It can therefore be seen that criticality will not be achieved by the cold water addition. Additionally, it should be noted that the most conservative (lowes t worth) value for control rod worth, less the most reactive rod, is approximately 7000 pcm or approximately 7% Ak/k. Thus, more shutdown margin is available than the required value of 1.774 ok/k.

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In conclusion, unisolating a loop in Mode 5 or 6 need not require that specific interlocks be met; however, fo added assurance of reactor safety, appropriate blender operation wi th a determination of shutdown margin, or appropriate samples ,

will provide a conservative approach to unisolating a loop.

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e i SUPPLEMENT TO ATTACHMENT B 9

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j INCEX LIMITING CONDITIONS FOR OPERATICN AND SURVEILLANCE REQUIREMENTS SECTION Pace 3/4.0 APPLICABILITY............................................. 3/40-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATICN CCNTROL Shutdcwn Margin - T,y > 200*F.......................... 3/41 ,

Shutdcwn Margin - T yyg 1 200*F.......................... 3/4 1-3 Scron Dil uti on-Reactor Ccol ant Flow. . . . . . . . . . . . . . . . . . . . . 3/a 1 -4 Ba rcn Dil uti on-Val ve Po si ti on . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-5 Moderater Temceratu re Coef fi ci ent. . . . . . . . . . . . . . . . . . . . . . . 3/4 1-6 Mi nicum Tempe ra tu re fo r Cri ti cal i ty. . . . . . . . . . . . . . . . . . . . 3/41-7 3/4.1.2 BCRATICN SYSTEMS F1 ow Pa th s - Sh u tdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/41-8 Fl ow P a th s - O p e ra ti n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/11-9 Charging Pump - Shutdcwn................................ 3/4 1-11 Charging Pumps - 0cerating.............................. 3/4 1-12 Soric Acid Transfer Pumps - Shutdown . . . . . . . . . . . . . . . . . . . . 3/4 1-13 B o ric Acid Trans fer Pum; s - 0cerating. . . . . . . . . . . . . . . . . . . 3/4 1-14 Barated Water Sources - Shutdcwn. . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-15 Scrated Water Scurces - Operating. . . . . . . . . . . . . . . . . . . . . . . 3/4 1-16 3 /4.1.3 MOVASLE CONTROL ASSEMBLIES Group Height............................................ 3/4 1-18 Pos i tion Indicator Channel s- Operati ng. . . . . . . . . . . . . . . . . . . 3/4 1-21 Pos i tion Indi cator Ch anr.el s- Shutdcwn . . . . . . . . . . . . . . . . . . . . 3/4 1-22

,od Drop Time....................... ...................

n. a/, 1 -,c S hu tdcwn Ro d In s e rti o n Li mi t . . . . . . . . . . . . . . . . . . . . . . . . . . 3/a 1 -2a Ca r.t rol Rod In s e rti on Li ni ts . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-25 NORM A'NA - UNIT 1 III

. , x ,

MMM nn 'n 'a s p a 11-26-77

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DEFINITIONS CHANNEL FUNCTIONAL TEST 1 .11 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

CORE ALTERATION 1.12 CORE ALTERATION shall be the movement or manipulation of any ccm-ponent within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not precluda cc=cletien of movement of a ccmponent to a safe ccnservative position.

SFUTECWN MARGIN 1.13 S*ajTCCWN c MARGIN shall be the instantaneous amount of reactivity by which tha eactor is subcritical or wculd be subcritical frem its present condition ssumig

a. d u ch:ng: in part 1:ngth red position, and

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- -h- [11 full length red cluster assemblies (shutdcwn and control)

. .are fully inserted except for the single red cluster assembly of

, , highest reactivity worth which is, assumed to be funy withd.rawn. .-

IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or talve packing leaks that are captured and conducted tn 7 su=p or collecting tank, or

b. Leakage into the containment atmosphere from scurces that are both specifically locatM and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or

c. Reactor coolant system leakage through a steam generator to the seccndary system.

UNIDENTIFIED LEAK [GE '

1.15 UNIDENTIFIED LEAXAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

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NORTH ANNA-UNIT 1 1-3

y ".q= 1 700R ORGN1 REACTIVITY CONTROL SYSTEMS _ . .

CHARGING PUMP - SHUTOOWN -

LIMITING CONDITION FOR OPERATION Nornere h n .

3.1.2.3 't 'crt one charging pump in the baron injection fic. Jath v.

- ~ - required by Specification 3.1.2.1 shall be OPERABLE, exept 4'o perroJ.s ;g-gr c3 he nch: evc<eec3 15 minute _ 3 y-' ---

. . APP 1_ICABILITY:- MODES

_.~. ;-- 5 =and 6. - - - .. ..__"~.

~~' ' --- I '

ACTION: .

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With no charking pump OPERABLE, suspend all operations involving CJRE ALTERATIONS.or positive reactivity changes. until one charging pump is restored to OPERA 8LE. status,. .

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, SURVEILLANCE REQUIREMENTS 4.1.2.3.1 At l east the above required charging pump shall be demonstrated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of > 2410 psig when tested pursuant to Specification 4.0.5.

4.1.2.3.2- M1 chc % nq pa,$ c , e <cep' 1.le dem veqnced ore WL~ pomp 3 s'no.!. 'o e de,m n.Acaed ( g g

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'ler' ln b .c h S'n e. sw :c'n e s in b e. C o n'w c), Roe n_,

have 'aeen p62 in b pai\ b 10a p%%n h,-

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3/4 1-11 12\0

.- NORTH ANNA-UNIT 1 i

P0ORORGNAL .

REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION The CobJn3 nom'cv o?

3.1.2.4 Tcharging pumps shall be OPERAP' E.

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APPLICABILITY: MODES 1, 2, 3 and 4' . , ,

ACTION:

F woi c.harf.ng pernps regared ed s (g) . With only one charging pump OPERABLE, restore a second charging pump to OPEPABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and barated to a SHUTDOWN HARGIN equivalent to at,least 1.77% delta k/k at 200 F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore a second charging pu=p to OPEP.ABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . The provisions of Specification 3.0.4 are not applicable for one hour following heatup above 340"f or prior to cooldown below 340 F.

32.o* F Sg'F (b) W& cne chocm.< c> cuma 4 d recy e_c , and no cMordnq pmo OPEFi ABLE 3 w a

, redore. one cbc.xmno pmp b OPC RG' E s'td:Us wi.Umm 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , cv- 'c e. In C.DL.D cpjTDOWN vMmn h neA 2.O 'ncers.

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SURVEILLANCE REQUIREMENTS 4.1.2.4.1 The above regtired charging pumps shall be demonstrated OPERABLE by verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 2410 psig when tested pursuant to Specification 4.0.5. g g p.or automch.tc. sbr -

4.1.2.4.2 All charging pumps, except the above required OPERABLE pump, shall.

be demonstrated inoperable t least.once per.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the temperature of one or more of the RCS cold legs is less than or equal to 340 F by verifying that the control switch is in ;he pull to lock position.

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\2\C NORTH ANNA - UNIT i 3/4 1-12

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'00RORGNAL

a. <, aaaa_a aa Sne RCS ccAd \e s Ono.n 320'F

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'b . One , exce g b pecmAs cr bte,e nok e .ceeAna is rni.n otes , wh e n h bencerluce

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'bC' one c,c r.more. c0h RCS Cold \eqs I.e \ ess b.c>:n or eoucA to 3Gb'c .

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POWER DISTRIBUTICN LIMITS SURVEILLANCE REOUIREMENTS (Continued' 4.2.1.3 The target flux difference cf each OPERABLE excore channel shall be determi.ted by measurement at least once per 92 Effective Full Power Days. The provisions of Specification 4.0.4 are not applicable.

a . 2.1. 4 The target flux difference shall be updated at least once per 31 Effective Full Power Days by ei'.ner determining the target flux difference cursuant to 4.2.1.3 absve or by linear interpolation between the most recently measured value and 0 percent at the end of the cycle life. The provisions of Specification 4.0.4 are not applicat.le.

\1\B NORTH ANNA - UNIT 1 3/4 2-3

I POWER DISTRIBUTION LIMITS SURVEILLANCE RECUIREMENTS (Continued) b) At least once per 31 EFPD, whichever occurs first.

R

2. When the F is less than or equal to the F x

1.imit for the appropriate measured core plane, additional power distribution R

maps shall be taken and F*C Y compared toY F*U and F*Yl'at least once per 31 EFPD.

e. The Fxy limits for RATED TliERMAL POWER within specific core planes shall be:

1.: F < 1.71 for all core planes containing bank "D" control rods cd/or ary part leg'b n dG and

2. eR P < l.55 for all unrodded core planes.

f. The Fxy limits of e, above, are not applicable in the following core plane regions as measured in percent of care height frca the bottom of the fuel:

1. Lower core region frcm 0 to 15%, inclusive.

2. Upper core region frem 85 to 100%, inclusive.

3. Gric plane regions at 17.8 + 2%, 32.1 + 2%, 46.4 + 2%,

60.6 + 2% and 74.9 + 2%, inBusive (17 x 17 fuel E ments).

4. Core plane regions within + 2% of core height (+ 2.88 inches) about the bank demand position of the bank "I'" & part kagt-h-control rods.

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g. With F exceeding F the effects of F on F evalualEd to determiEl q if F (Z) is withidYits19m(Z)sha it.

4.2.2.3 When qF (Z) is measured for other than F xy determination, an overall measured Fq (Z) shall be obtained frca a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

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A?PLICABILITY- M00E 1 A50VE 50% CF RATED THERMAL PCWER*

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a. With the QUADRANT POWER TILT RATIO determined to exceed 1.02 but _< l.09:

l. Within 2 hcurs:

a) Either reduce the GUADRANT F0WER TILT RATIO to within its limit, or b) Reduce THERMAL PCWER at least 35 from RATED THERMAL .

vc,a.t 3. . rcr eacn ,i .. o r i nc1 cated p;L,e,nRn...-

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-ta R ii,.i l F.ATIO in excess of 1.0 and similarly reduce the rower mange d, eutron r,iux-d. ign i ri dp etpoints wi tnin the nex: 4 neurs.

ri ty tn2' -"a y g.

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.r,u n.ml i r .a:R i t , i anit c . . ,,-.0 is w1.nin its.

limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding tne limit or red.ca THERMAL PCWER to less than 5C% of RATED THERMAL POWER wi nin the nex: 2 hcurs and reduce the ?cwer Range Neutron Flux-Hich Trip setccints to < 55% of RATED THERMAL FCWER within the next a hours.

3. Identify and c rrect the cause of the cut of limit con-dition criar cc increasing THERMAL PCWER; subsequent

.p egr n a h.c Ve v - a n..:::' -. -,7 t .1 . 0". o f Dm' ~ 0 TP. :. ..v.AL 00".u'. . .,ay prcceed ;rcvided that the QUADRANT POWER TILT RATIO is verifiec wi-hin its limit at least cnce per hcur for j 12 hcurs or until verified accectable at 955 cr grea:er i RATED THERMAL POWER.

b. .iith the QUADRANT PCWER TILT RA~ td determined to exceed 1.09 cue to misalignment of either a shutdown -control or-part length red: c-

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for each 1% of indicated QUADRANT PCWER TILT RATIO in excess of 1.0, within 30 minutes.

2. 'ierify that the QUADRANT PCWER TILT RATIO is within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after exceeding :ne limit er

'See 5;ecial Test Excec:icn 3.10.2.

NORTH ANNA - UNIT i 3/d 2-12

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P00RORGE.

POWER DISTRI3UTION LIMITING CCNCITICM FOR OPERATICN (Centinued) reduce THERMAL POWER to less than 50% of RATED THERMAL

?OWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and recuce the Power Range Neutrcn Flux-Hich trip 5etcoints tc _< 555 of RATED THERMAL POWER witnin the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3. Identify and correct the cause of tne out of limit can-dition prior to increasing THERMAL POWER; subsecuent POWER OPERATION above 50: of RATED THERMAL PCWER may proceed provided that the CUADRANT POWER TILT RATIO is verified within its limit at least once cer hour for 12 hcurs or until verified acceptable at 955 or greater RATED THERMAL POWER.

c. With the CUACRANT POWER TILT RATIO determined to exceed 1.09 due to causes other than the misalignment of either a shut-dcwn , control on-part-1.ength rod: l m-

1. Reduce THERMAL POWER to less than 505 of RATED THERMAL

, POWER within 2 : 'urs and reduce the Pcwer Range Neutron Flux Hign irlp Setacints to < 55 of RATED d THERMAL PCWER w i tn. .in tn.e nex:.a.nours.

2. Identify and correct the cause of the out of limit con-diticn prior to increasing THERMAL PCWER; subsecuent PCWER OPERATION above 50% of RATED THERMAL POWER may l pecceed provided that the QUACRANT POWER TILT RATIO is verified within its limit at least once per hcur for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at 955 or greater RATED THERFAL POWER.

3.-.,-.,,a,,- y-.e.l l 3 a l l . . -. 6LO M OL,U L ML a.2.4 The QUACRANT POWER TILT RATIO shall be determined to be within tne limit above 50% of RATED THERMAL PCWER by:

a. Calculating the ratio at least once per 7 days when the alarm is OPERAELE.

b. Calculating the ratic at least once ; r 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady state aceration when the alarm is inoperable.

c. Using the movable incere detectors to ccafirm that the ;cwer distribution is consistent with the indicated CUADRANT POWER TILT RATIO at least once per 12 hcurs when one ?cwer Range Channel is incoerable and THERMAL POWER is > 75 percent of RATED THERMAL POWER.

NORTH ANNA - UNIT 1 3/4 J.-13 -)k\

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. ?00R ORGINAL REACTOR CCOLANT SYSTEM ISOLATED LOOP STARTUP LIMITING CONDITION FOR CPERATION

3. 4.1. 3 A reactor coolant loop cold leg stop valve shall remain r.:tosed until: .

a. The isolated loop has been operating on~a recirculation flow of 3.125 spm for at least 90 minutes and the temperature at the cold leg of the isolated loop is within 20*F of the highest cold leg temperature. ' ,

- vD l

' b. The reactor is suberitical by at least 1.77 percent ak/k.

.., APPLICABILITY: MODES , i. ,2. , 3, e ,d 4.

ACTION:

With the raquirements of the above specification not satisfied, suspend startup of the isolated loop.

SURVEILLANCE RECUIREMENTS 4.4.1.3.1 The isolated loop cold leg temperature shall be determined to be within 20*F of the highest cold leg temperature

.uithin 30 minutes prior to opening the cold leg stop valve.

A.4.1.3.2 The reactor shall be determined to be subtritical by at least 1.77 percent ak/k within 30 minutes prior to opening the cold leg stop valve.

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NORTr! ArctA - UNIT 1 3/4 4-5 \

P00R OHNM REACTOR C00LUli SYSTEM 3/t.t.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLA?ti SYSTEi LIMITI?;G CO?IDITIOff FOR OPERATI0ft 3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2 and 3.4-3 during heatup, ccoldown, criticality, and inservice leak and hydrostatic testing with:

a. A maxt: a heatup of ICO*F in any one hour period.

b. A maximum cooldcwn of 100*F in any one hour period.

A PPLICA3ILITY : At all times.

ACTIO?i: b E.E kTTACHED bHEF With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the cut-of-limit condition on the fracture toughness properties of the Reactor Coolant System; determine "that the Reactor Coolant System remains acceptable for continued operations or be in at least HOT STAT 1C3Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce the RCS T and pressure to less than 200*F and 500 psig, respectively, within tMSfollowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLA? ICE RECUIREME'ITS

4. 4. 9.1.1 The Reactor C-colant System temperature and pressure shall be detemined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations .

4.4.9.1.2 The reactor vessel material ' radiation surveillance specimens shall be removed and examined, te determine changes in material properties, at the intervalsbhca 'n Table t.; ShThe results of these examinations shall be used to update Figures 3.4-2 and 3.4-3.

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1T ~~ _1 2000 E:2=E LEAK TEST LivlT 7___,_-._w__,-----___ ._-_.., . . _ _ . . _ .

.__________j .

__p____ _.

--=]i2-- 2 ._____._..__~_3 tra_ _ _ . .

{

=----*

~ - - - - - -

_ _ _ . _ _ _ _ _ . .:- = =__ . .

((, _,; _ _ _ . _ __ _______ _ = = r=:=nt

. - _ - - - .U -= NAC r==

C E P T A B L E re-__,. _ . 2 = -: : r _ r=

=:- = == :

MN} CP ER ATiON ~7TCZ 225 - ACCEPT ABLE b-5~;5 h SNY Z $$En$$25- - - - - - - -

-~

CDER ATION

_=.-=:^=2~_=-E. t

..._____.___...__.._=_=_

1.n U ===.u==:=_=_=___.___.._u.===._2.-

' - : -- :- r == _ . _ _ _ .

==: . _ .

_l-~ ~ _- VC OE S 1.2.3. 70 4 E i-

~

E ME ATUP R ATE UP TO 100 (C:_ _ . . _ . . . _ _ _ _ ' _, H a l s

_;._..___

-1 _ _ _ _ _ .

O [E=-

'~Z _ .iE 5 _i=_r-~ '~ ~~ ~~; =: ~======='== .===,t_..-.=---:

w L=-

==-"

1000 't.-___:== __. -- :_;:-- -_:=-=u===--=:~-~",u==__=~--'~-

-=====:==~'__ r

t

< :r_--

: ==:-- r --]

y t- _ 1. - -+ -- x=n- - - - -

.,-t_-

.= : . _

g ==2 4-- -_:----=--+---=t= =:= : - n- - s n ----*) -

+

u ;----_-.==:==._.._

P .-

_ _ . _. ,_ _ ._. ._ . . _ _. _ _ . _ = _ ....._ CRITIC AllTV LIMIT r.;;-3 Z -^ M =.=c__ __w=.=

i= E='-- - - - -

- . =-.-.=-.-- -~ - - = =-== =- -_ =

_-+ _ _ _ _:

r= --

= = b = . ._ _ . _ =- - -_m_ ---

. ,._ _ _..___..__. -- _g;-;;_---- - _ _ _ -

lE too-1 n

-- ___ c---2 e_ _ _ . . _ _ _ _ _ _ . . _ _ . . . . _ . - _

==m = = _ . . _ _ _ . . ..__.__.__-:-_=__--2 P E --. -..Ac:eMao'e Operat Cn_____~'_-~~-Q-___,_ ____.___._-*:--C_.y --'*]~_

r -= .-- voces 3.4, and 5

- . - _ . - = - - - - EE_:E._=_ '- n_ ._: IEx:===!

=;===- === , :

=:=---------------.-----._:

c===.-_:-*-_n.__=___:===n__..

t=znr . :

m n .=:---==.----

O p====..

_-:___=_=.r

_ . - . . . _ . . _ . . _ _ _ = -=2==--r__._,._=.._._3 100 200 300 a00 500 0

INDICATED TEMDERATURE (OF)

Figure 3.4-2 Reactor Cociant System Temcerature-Pressure Heatup Limitations NORTH ANN A-UNIT I 3/4 4-27 e

e O. -

u

s

! TABLE 4.4-5 51

,, REACTOR VESSEL ltATERIAL !RRADIATION SURVEILLANCE SCHEDULE _.]

' CAPSULE _ REMOVAL INTERVAL E ~T q 1. W 1st Refuelin g)

2. X 15 year r

3. T 2 cars (Reinsert in Location W) "y

-l

4. S 20 years (Reinsert in Location X) _

5. V 25 years hg

6. Z 30 years (Reinsert in Location V) k R. _t

? 7. U (Extra) 5 0 1

8. Y Extra) 7 F

- 4 (T) r F

/ Z N X

- w ,

C 5/ -

r . q. .. -

~

700ROR8NAL REACTOR COOLANT SYSTEM l OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection systems shall be OPERABLE:

Los

a. Two power operated relief / valves (PORVs) with a lift setting of: 1) ,

less than is less or equal than to(435psig or equal to FJ, andwhenever

2) lessany RCS than cold leg or equal to temppsig

@erature

+

whenever any RC3 cold legftemperature is less than 140 F, or 43o 32.o*F

b. A reactor coolant system vent of greater than or equal to 2.07 square inches.

iPPLICABILITY: When .the temperature of one or more of the RCS cold legs

- is less than or equal to 3M f, except when the reactor vessel head is removed. 32c'F ACTION: {.% 90% re- bd A

a. With Yone PORV inoperable, either restore the inoperable FORV to OPERABLE status within 7 days or depressurize and vent the RCS through 2.07 square inch vent (s) within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the.RCS in a vented condition until both PORVs have been restcred to OPERABLE status. .

b. With both PORVs inoperable, depressurize and vent the RCS through a 2.07 square inch vent (s) within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in a vented condition until both PORVs have been restored to OPERABLE status.

c. In the event either the PORVs or the RCS vent (s) are useo to mitigate a RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days'. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent (s) on the transient and

.any corrective action necessary .to prevent recurrence.

d. The provisions of Specification 3.0.4 are'not applicable.

%l g\ D' NORTil ANNA - UNIT 1. 3/4 4- 90ct

REACTOR CCOLANT SYSTEM I

w31 UIni U Hj'l SURVEILLANCE REOUIREMENTS 4.4.9.3.1 Each PORV shall be decaanstrated OPERABLE by:

a. Performance of a CHANNEL FUNCTICNAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required CPERABLE and at least once per 31 days thereaf ter when the PORV is required OPERABLE.

b. Performance of a CHANNEL CALIBRATION on the PORV actuation channel, at least once per 18 months.

Poav kepskb is in % NUTO pcshn , and be.

c. Verifying the'IPORV isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months when the PCRV is being used for overpressure protection.

d. Testing i pursuant to Specification 4.0.5.

~

4. 4. 9. 3. 2 The ,RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent (s) is being used for overprassure protection.

?Except when the vent pathway is provided with a valve which is locked, scaled, or otherwise secured in the open position, then verify Ge vedve(.s) cpen c1 \ead. cnce, fe" 31 days Nnen 'cew3 used -e I c c,ver crescu re. pechabien .

9

\1\Q -

NORTH ANNA - UNIT i 3/4 4- Sob ,

~

700RORGEL EMERGENCY CORE COOLING SfSTEMS ECCS SUB5YSTEMS - T ava < 3507 LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE: . .

a. One OPERABLE centrifugal charging pumpf

b. OneOPERABLEIcw.headsafetyinjectionpumpiand

c. An OPERABLE flow path capable of transferring fluid to the reactor coolant system when taking suction from the refueling

. water storage tank upon being manually realigned or from the -

containment sump when the suction is transferred during the recirculation phase of operation or from tae discharge of the outside recirculation spray pump. 2 APPLICABILITY: MODE 4.

. . ACTION:

a. With no ECCS subsy. stem 0PEPABLE because of the inoperability of either the centrif'ugal charging pump or the ficw path from the refueling water storage tank, restore.at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD f,

SHUTDOWNwithintgenext20 hours.

1 <.

b. With no ECCS subsystem CPERABLE b.ecause of the inoperability

~

of the icw head safaty injection ' pump, restore at least one ECCS subsystem to OPERABL.E sta W1 or maintain the Reactor Coolant System T. l

.) heatremovalMethUs.essaha(350Fbyuseofalternate "

c. . In the event the ECCS is actuated and injects water into the s

Reactor Coolant System, a Special Report. s' hall be prepared and submitted to the Comission pursuant to Specificaticn 6.9.2 r within 90 days describing the circumstances of the actuation and the total accumulated actuation cy.cles to date. , ,,

BEE ATTA.CGD $HEET 3 SURVEILLANCE REQUIREMENTS t_::: -

4.5.3.iThe ECCS subsystem shall be demonstrated OPERABLE per the appTicable Surveillance Require.-ents of 4.5.2. -

SEE Nrmac 9aT NORTH ANNA-UNIT 1 3/4 5-6 1210 249

e

~

?00RORGNAL

No more 'dnc~n one. cen'en.?ac.cd chcxrainq purnp and one \ow Inead sY0ely inecden pueno s'ncdl be. OPERABLE , ex'ceph er-periods cP time. nck b exe ed is minaes, wdnenever 'dne_ hempeccioce_ oCone ov-rnere. cP Ehe R C S c alc! \e c p iss less b n c>r eoea\ o 32.0 F

\

4.5.2.2. Ni cjna y n3 oocnps cmd ecSel 7

the ob e~e.

uc,3ecten puenps 3 e_xc_e.pt '

reqmeec\ OPERELE purnes, dncat 'o e.

de.rnens'trche_ck 'LnopercMe br- Oslornc1Lt.

s'taA ck \ecsk once. pe c 12. hoort ydnenever he kernperJ1oce. oC one. or more oc the. V,ts coq !eos i.s less b n cr eau.cd ho 32D F ov derL?mn Sci f

Sheer swiic\nes un Un[ Contr(( co m cxte b, be puu b lock pos0cten 1210 250

9 4 300RORGINa CCNTAIMMENT SYSTE'45 WASTE GAS CHARCCAL TD.TER SYST~M LIMITING CCNOITION F R OPERATION 3.5.4.3 A waste gas charecal filter system (shared with Unit 2) shall be CPERABL APPLICASILITY: MCDE5' land 2.~ -

ACTICN: _.

'dith the waste g$} charcoal filter system inocerable, restore the inecerable system to OPERA 8LE status within 30 days or be in at least HCT STANCSY within the next 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . .

. 4

} SL://EILLANCE RECUIREMENTS 4.5.4.3 The waste gas charcoal filter system shall be demonstrated OPE AELE:

0

! a. At least ence per 31 days by:

1. Initiating flew thrcugh the HEPA filter and charcoal adsorter train using the process vent blewers and veri-fying that the purge system operates for at least 15 minutes, i

b. At least once per 18 months or (1) after any structural :r.ain-tenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation ::ene ccmunicating with the system by:

1. Verifying that the cleanuo system satisfies the in-place l testing acceptance criteria and uses the test proceduras I of Regulator 1 Positions C.5.a. , C.5.c and C.S.d of Regula-tory Guida 1.52Qc.isjcp 1, h!L E75, and the system {

ficw rate is 3C0 cfm f.10% (e.uet s rJnc on tn SpecAcebs 4.G.4.3.e. ond I. G.a. 3.C ).

been 2, %.w me .

9~3c\

NCRT'-i ANNA - UNIT 1 3/4 6-35 g\B 1

(Page previously submitted)

P00RORGNAL CC ITAI.'iMENT SYSTEMS SURVEILL:11CE RECUIREMENTS (Continued)

2. Verifying within.31 days af ter removal that a laboratory analysis of a representative carbon sample obtained in accordance with Reculatory Position C.6.b. of Regulatory Guide 1.52 Cc,isica 1, Li,1:M meets the laboratory -

testing criteria of Reculatory Position C.6.a. of Regula-tory Guide 1.52,[Retision 1, C A,1:75 ..

g- 4g Verifying a system ficw rate of 300 cfm 110% during ..

- 3. . . _ _

.. system aceration when testad in acccrdance with ANSI N 510-1975.: : 2. .; - ' ,

^

c. After every 720 hcurs of charccal adsorber operation by -

verifying.within 31 days after removal that a laboratory analysis

!' of representative carbon sample cbtained in accordance with ..

-- Reculatory Position C.6.b of Regulatory Guide 1.52,@e a;i d,p"" g

, Mar 6 935L% .9% meets the laboratory testing criteria of Reculat. v Position C.6.a of Regulatory Guide 1.52,@e,i ica 1, C4 1:.9

! d. At least once per 18 months by: R*

i f 1. Verifying that- the pressure-dren across he HEPA filter ind i

charcoal adsorber assembly is Q8.5 inches Water Gauge while cperating the filter trainiat a flew rate of 300 cfm I

-+ 10%.

less b n

,) e. After each ccmplete or partial replacement of a HEPA filter 8

bank by verifying that the HEPA filter banks renove 1 99% of

- the DOP when they are tested in-place in ordance with ANSI N510-1975 while operating the system at . .lcw r ~ of-300 cfm + 10%. ~

I

' f. After each ccmplete or partial replacement charcoal adsarber bank by verifying that the charcoal adsorbers remove 1 99". of a halogenated hydrocarbcn refrigerant test gas when they are tested

, in-place in accordance with A? SI ! 510-1975 while cparating the i system at a ficw rate of 300 cfm 110%.

i

}

l NORT'i A?iNA - UNIT 1 3/4 6-26 g g 252 ,

(Page previously submitted)

. ~

~

?00RBRGNAL PLUtT SYSTEMS 3/4.7.7 CONTRCL RCCM EMERGENCY HABITABILITY SYSTEMS LIMITING CONDITICM FOR OPERATICN (S h ed w b b 1 Mc>. 2Y )

3.7.7.1 The folicwing control racm emergency habitibility systems shall be OPERABLE:

.i

a. The emergency ventilation system. ,

b. The bottled air p'essurization system,

c. Two air conditiening systems.

APPLICABILITY: MCDES 1, 2, 3 and 4. ,

CcE kTi@pHED bHET ACTICM:

"'5 tither th:--r.crgency '!:nthtien cyst:- or t . tetti d :f p ::

k

- : ri:: tion systen-and :n air.cenditioni g systr #90;;r:5I , : t:rc th: in:;;r:bl: :y t s-t CT LE s ta tu ,Ithi ' d j or b f- it h-ast-iiOT ST?:;3EV-AMn-the-next-6-hours-end in CCLC SE'7C'.!" ithin the-4c 11 : .? ,; 22 ' . u - .

SUR'lEILLANCE RECUIREENTS ~~

I 4.7.7.1 Each ceneci recm emergency ventilaticn system shall be damen-strated OPERABLE:

~ .

a. At least cnce per 31 days an a STAGGERED TEST SA5IS by initi-ating, fecm the control recm, flow through the HEPA filters and charr.::21 adscrberjsrtd. verifying that the syste= cperates

at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters on.

~~

b.- At least cnce per 18 months or (1) af ter any structural mHn-i tenance on the HEPA filter or charcoal adsorber housings, or

'(2) following painting, fire or chemical release in any venti-laticn :ene cecrunicating with the system by:

1. Verifying 'that the cleanup system satisfiks the in-place testing. ac::eptance criteria and uses the test precedures of Reculatory Posjtions C.S.a, C.S.c and C.5.d of Regula-f tory Guide 1.52ktey+sta 1, J+ 1, ICM), nd the system flow rate is 1000 cfm i 10". 'a,cd 3,3 gg' n

.3pecMicc2non 4.~l.li.e cnci 4.' '7.1.{),

Redsten 7-, Mctcch '.ME

' MORTri ANNA - UNIT 1 3/4 7-El Q h) . '~h ,.

P00RORGNAL

?.i - ,\ \ ., \ L O.\As..1n es\ \'er tne emeraent tr ver th ,qnc,n G75 M.-, or

~

% bauel ai.c pressordchn sy s 6 i.n g e W e ,

.s ,

i _ _ _

ICstCPE IOtd knCOtF" d 2.C b'!bttfn EO h N:\b O b.t LOS 1

'N'.~.n gri ] dGjs QC '2 C. kn C \tCLSI., OI bYDbbY vi\.'rin Yne rid L nours onci in ch Ieosh C.0LC ERUTDa\\'M wu.'nin ne ?c\\cwtnq 3D 'ncucs.

e O. Ltn CG tt Cch tr CG C.'. 'lentOC TOG E 6 CM Of%O 6.e be'Jed c3.c onssonic' con sys'am inoperck\e, redore_ o't \eos't one oC Enese sydems ic DPERABLE

((rius wiVrin 2A 'hcors De he' ir, c& \eced HOT ST.aNDSY wl9nin Vnt n e' d L n e urs o n c e n cub teas! totn sauross~si n'cntn Vnt ?caew<noJ 20 'c'ours.

C. S $n One O'\r CCndl.'deni.nq 'sys' tem. L,ccerch$e ,

1 Ptdu3re En trecerd'o\t. h shem

, /

1.3 ONERPSLE shch.us wc-n n 7 cays er 'oe in ca lead rot STetosy Ph20e kne nuk (o ' hours Gr in $h I,SQ5t OCLD

$HUTD0'.NN Wi.YntG 'O^1t Ec\\cvienr 3D 'nours a

i .

1 ,,

d . b. en co .n OLr tona,.v.octr.o S'jstems tnoperade 3 redere o\. \eos't one sys\ terry b BPERetE shAus wi9ntc. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be i.n ck \eos't STANDSY

~

wAn be ned. L 'nauts and :.n ai teos. Coto suoToom wAn % fenesco 30 \ .cors.

%4 n\D

se

~ ~ ~

300RORGNAl.

PLANT SYSTE'4 SURVEILLANCE REGUIREMENTS (Cont'd)

2. Verifying within 31 days af ter removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulafory Position C.6.b- ef Reculatory --

Guide 1.52,C:i;ior1, July 19757meetsthelaboratory 7 l testing criteria off Regulafory Position C.6.a of Regula-l tory Guide 1.52,(Ra icica 1, ' 1,1MgReves cn 2, %en Ph8 l -

. 3. Verifying a. system flow rate of 1000 cfm 110% during system operation when tested in accordance with ANSI N510-1975. * \

c. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months bf charcoal adsorber operation by verifying.

within 31 days after. removal that a laboratory analysis of repre-

. sentative carton sample obtained in accordance with Regulatory Position C.S.b of Regulatory Guide 1.52, C'c.ision .,Ju., '? M +

meets the laboratory testing criteria of _Reculatory Position C.S.a of Regulatory Guide l'.52, C:.i;;;n 1, J E '?"t

d. At least once per 18 months by: %vsten 2 J Aarc'n WIBs

, , 1. Verifying that the pressura drop across the HEPA filter

, , and charcoal adsorber assembly is < 6 inches Water Gauge white operating _the filter train at a flow rate of 1000 cfm + 10%.

2. Verifying that thi normal air supply and exhaust are '

-l automatically shutdown on a Safety Injection Actuation Test Signal.-

t .

3. Verifying that the system maintains the control room at a positive prussur of > 0.04 inch W. G. relative to the

~

outside at=osphere at a sy3fam flow rate of 1000 cfm + 10%.

.i/ e .. After each complete or partial replacement of a HEPA__ filter bank ,-

J by verifying that the HEPA filter banks remove > 99% of the 00P

when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 1000 cfm + 10%.

f. After each complete or partial replacement of a charc:;al adsor-i ber bank by verifying that that charcoal adsorbers remove > 99%

~

of a halgenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operat-g ing the system at a flow rate 'f 1000 cfm 110*.

Y NORTH ANNA - UNIT 1 3/4 7-22 g [*h '

~

200RORGNE PLA?1T SYSTEjjs, 3/4.7.8 SAFEGUARDS AREA VEllTILATI0fl SYSTEM LIMITIllG C0tt0ITI0fl FOR OPERATI0tl 3.7.8.1 Two safeguards area ventilation systems (SAVS) shall be OPERA 3LE with: , . . .

a. one SAVS exhaust fan

b. one auxiliary building HEPA filter and charcoal adsorber assembly '(shared with Unit 2)

APPLICABILITY: MODES 1, 2, 3 and 4 -

ACTIC?l: 's

\

With cne SAVS inoperable, restare tne inoperable system to OPERABLE status within 7 days or be in at least HOT STAtiCBY within the next 6 hcurs and in CCLD 5:UTCC'WN within the folicwing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLAtiCE .ECur?I s1TS 4.7.8.1 Each SAVS system shall be demonstrated OPERABLE:

a. At least cnce per 31 days en a STAGGERED TEST BASIS by:

1. InittiIting, frem the control recm, flow thrcush the auxiliary building HEFA filter and charccak-adsorber assecbly ;nd verifying that the SAVS operates for at least 1G hours with the heater on. .

, b. At least once per s or (1) after any structural maintenance on the HEPA filter or charecal adsorber. housings, or (2) folicwing painting, fire or chemical release in any ventilation zone ccm:u_nicating with the system, by:

1. Verifying that the cleanup system satisfies the in-place testing acceptance criteria v;d uses the test procedures of Regulatory Positions C.5.a. C.S.c and C.5.d of Regula-tory Guide 1.52,'Oc' if en 1, Jub '94 and the system flow rate is 6,300 cfm ;10% ( end ce c-hewn M Spec 1ccMc,n 4 ' S. i.e. cwyl 4.7.' E.1, 9 ). 'T

' R.ene,wn 2 , Nbcx 13 7B /

tt0RTH At;ttA - UtiIT 1 ')hD 3/4 7-24 QS .

~

J PLANT SYSTEM SURVEILLANCE RECUIREME.'ITS (Cont'd)

2. Verifying within 31 days after remov_al that a laborato

-analysis of a representative carbon sample obtained in_ry accordance with Regulatory Position C.6.b of Regulatory Guide 1' 52KRens4en ', A ,107% meets the laboratory.

testing criteria of Regulatory Position C.6.a of Re-gula ~ .

tory Guide 1.52,U.:vi ica

~

., Li, ::75.

C Revan 2s N^occh BW J

3. Verifying a system flow rate of 6,300 cfm + 10% during

'peration when tested in accordance with AfiSI N510-1975.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by veri-c.

fying within 31 days after removal that a liberatory analysis of representative carbon sample obtained in accordance with -

Reculatory Position C.5.b of Regulatory Guide 1.52,U:/'c' "

+ 1. Li,1:73 meets the laboratory testing criteria of Recula_-

tory Positicn C.6.a. of Regulatory Guide 1.52,(Rc;i:ior 1, Aly t - Rev ssbn 2. , W n W7 S d.. At least once per 18 months by:

1. Verifying that the pressure drop across the HEPA filter

- and charcoal adsorber assembly is < 6 inches Water Gauge while operating the ventilation system at a flow rate of 6,300 cfm + 10%.

c .

2. Verifying that on a Containment Hi-Hi Test Signal, the systect.autc=atically diverts its exhaust flow through the auxil'iary building HEPA filter and charcoal adsorber assembly. _

e. After each ccmplete or partial replacement of a HEPA filter bank I by verifying thatJeAtEPA filter banks remove > 99% of the COP vhen they are tested in-place in accordanAe.with AllSI N510-1975 while ope' rating the system at a flow rate of-6,300 cfm +10%.

,- f. After each ccmplete or partial replacement of a charcoal adsor-ber bank by verifying that that charcoal adsorbers remove > 99%

of a halgenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-lG75 while operat-ing the system at a flow rate of 6,300 cfm t 10%.

9' s'D HORTH Anna - UNIT 1 3/4 7-25 .

e

'~~

~

P00R 01B R

)

i SPECIAL TEST EXCEPTI0 tis POSITION INDICATOR CHArl?!ELS-5HUTDCW:1_

LIMITING C0fiDITICN FOR OPERATICN 3.10.5 The limitations of Specification 3.1.3.3 may be suspended #uring the performance of individual full length (shutdown and control) rod drop time measurements provided; .

., - a. Only one shutdown or centrol bank is withdrawn from the fully inserted position at a time, and

b. The rod position indicator ic OPERABLE during the with-

'drawal of the rods.* l

APPLICABILITY: MODES 3, 4 and 5 during performance of rod drop time measurements.

' ACTION:

With the position indicator channels inoperable, or more than one bank of rods withdrawn, immediately cpen the reactor trip breakers.

L SURVEILLANCE REQUIREEllTS

10.5 ^: 15 eve-+egi d rcd p :ition 4ndicatcr char 21: :hai' te deter ' -d t: 5: 0 'f5LE h. :: ##;' 3 th d: ard :: : '-d'::tica

'2 :t:;

:te 2-d t': Od p iti - indicat:r c' r i: gr:0 4t

"dt"4- 2* 5:;r: prj:- t: tP st:-t :# cd drop tit: :::;r: rant and at 1:: t ent: p:r 2" h Lr: th rt:f t:r; SEE TTACMD SMEET NORTH ANNA - UNIT 1 3/4 10-5

)h 3liG

~

?00R OR E L 4 10. 5 Tne red posten :.nkcacon c? cove. re'\ meed systecns s'nd be. deterwned 6 be oPeaNat E wAn 2.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior lo the. ehach of ond ok \eas't once pec 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Mnecech durLng rod drop kirne rnectsurernents verJ tnaJ vune cernc<nc\

.\. . \. .. 'bY , 7 n postuon snd t.c.ccon 57citern cmd 4.e. rod poshn inc!cccMon sysberns ctcpe ,

cs. W d.non 12. cd.eos w'nen Sne. eods ore _

Shohlonor ., 0.n c

'o. W@nto 24 sters F c'iucino red mckte n .

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$ t s

-' hiS ce t siee .m e nu LL n Ct C c 5.iC.N.o\e.

do rt.n Noe Un'd.iol c d [h rckCo n C 9 N n e.

rod ostlic>n i.ncM.cc h n. svs .e.cn p ro -

Vic\ec\ (O hece i.s mcin' toiMeA 1ess Onan or equa\ b O. \cs ., and CO on\7

. one dnukac,wn c>r cc>n%\ red beex i.s wiBdrc,wn b cn b e S L\\, 'nse u &d pos0ti.cn el one be .

1210 259

~ ~

~ ' ~

?00R BRIUJL 9

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 BORATION SYSTEMS (Continued) .

With the RCS average temperature above 200*F, a minimum of two

~ separate and redundant bcron injection systems are provided to ensure single functional capability in the event an assumed failure renders one

, of the systems inoperable. Allcwable out-of-service periods ensure that ptinar compenent repair or corrective action may be completed without undue risk to overall facilit'y safety from injection system failures

during the repair period.

The boration capability of either system is sufficient to provide a SHlITDOWN PARGIN from expected operating conditions of 1.77% ak/k after xenon decay and cooldown to 200*F. This expected boration capability requirement occurs at EOL from full pcwer equilibrium xenon conditions and requires 4450 gallons of 20,000 ppm borated water from the boric acid storage tanks or 70,000 gallens of 2000 ppm borated water from the refueling water storage tank.

, With the RCS temperature below 200*F, one infection system is acceptable without singTe failure consideration on the basis of the stable reactivity condition of the reactor and the additional restric-tions pmhibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.

The baron capability required belcw 200 F is sufficient to provide i a SHUT 00WN PARGIN of 1,77% ak/k after xenon decay and cooldown from 200*F l to 140*F. This condition requires either 835 gallons of 20,000 ppm borated water from the boric acid storage tanks or 9690 gallons of 2000 ppm borated water from the refueling water storage tank.

The contained water volume limits include allowance for water not avaiTable because of discharge line location and other p,hysical character-istics. The OPERABILITY of one baron injection system during REFUELING insures that this system is available for' reactivity control while in MODE 6. g,r3 9.0 The limits on contained water volumehand baron [ concentration of the RWST also ensure a pH value of between Ed and Th0 for the solution ,

recirculated within the containment after a LOCA. This pH minimizes the evolution of iodine and minimizes '.he effect of chloride and. caustic stress corosion on mechanical sy, stems and ccmponents.

g NORTH ANNA - UNIT 1 B 3/4 1-3

3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this secticn provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Mcderate Frequency) events by: (a) maintaining the minimum DNBR in the core > 1.30 during normal operation and in short term transients, and (b) limiting the fission gas release, fuel pellet temperature & cladding mechanical procerties to within assumed design criteria. In addition, limiting the peak linear pcwer density during Condition I events prcvides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200*F is not exceeded.

The definitiens of certain hot channel and peaking factor: as used in these specificaticns are as follcws:

Fg(Z) Heat Flux Hot Channel Factor, is defined as the maximum lccal heat flux on the surface of a fuel rod at care elevation Z divided by the average fuel rod heat flux, allcwing for man-ufacturing tolerances en fuel pellets and rods.

~

4 F "q Nuclear Enthalpy Rise Hot Channel Facter, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power.

Radial Peaking Factor, is defined as the ratio of pet power F.7(Z) density to average power density in the horizontal piene at core elevation Z.

3/2.2.1 AXIP. FLUX DIFFE9ENCE (AFD)

The limits on AXIAL FLUX DIFFEP,ENCE assure that the F0 (Z) upper bound envelope of 2.21 times the normalized axial peaking ractor is not exceeded during either nomal operation or in the event of xenon redis-tribution following power changes.

Target flux difference is determined at equilibrium xenon conditions.withl the-part-length-contro4-rods-wi-thdrawn from-the-cara The full length rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their nomal position for steady state operaticn at high power levels. The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup conditions. Target flux differences for other THERM.AL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level. The periodic updating of the target flux difference value is necessary to reflect core burnup considerati,ln;;.lo 1210 NORTH ANNA - UNIT 1 B 3/4 2-1

_PCWER DISTRIBUTION LIMIT 5

-3ASE5 3/a.2.2 and 3/2.2.3 HEAT FUJX AND NUCLEAR E'1 THAL?Y HOT CHANNEL FACTCRS-U F0 (I) and F aH The limits on heat flux and nuclear enthalpy hot channel factors ensure that 1) the design limits on ceak local pcwer density and minimum CN8R are not exceeded and 2) in the event of a LCCA the peak fuel clad temcerature will not exceed the 2200*F ECCS acceptance criteria limit.

Each of these hot channel factors are measurable but will nor ally only be determined pericdically as sc-_ified in Scecificaricns 4.2.2 and 4.2.3. This periodic surveillance is suffi-ient to insure that tne hot channel factor limits are maintained provided:

a. Control red in a single grouc move together with no individual red insertion differing by more than i 12 steps frca the groua demand positicn.

5. Control red groups are sequenced with cverlaccing groucs as described in Specification 3.1.3.6.

c. The control red insertien limits of Specifications 3.1.3.6 ,

and-3Ar3r7 are r:.aintained. i

d. The axial cower distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.

The relaxaticn in Ff. as a a function of THERMAL PCWER alicus changes in the radial ccwer shace"for all permissible red insertion limits. :"y will be maintained within its limits provided ccnditions a thru d abovd, are maintained.

When an F measurement is taken, both experimental error and man-ufacturing toihrance must be allcwed for. 5% is the acpropriate allcwance for a full core r..ap taken with the incere detector flux mapping system and 35 is the accropriate allowance for manufacturing tolerance.

1 When Fi is measured, excerimental error must be allowed for and 45 is the acor:qDr'?te allowa nce for a full ccre .up taken with the incore detection system. The specified limit for F;y H isc contaSs an F.

alicwance for uncertainties which mean that normal oceration will cesul in F < 1.55/1.08. The 5% alicwance is based en the folicwing con-side $$tTons:

2\C 2M, NCRTH ANNA - UNIT 1 8 3/4 2 a 300RORGNAL

BASES The OPERABILITY of two PORVs or an RCS vent opening of greater than 2.07 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs is < 320 F, and the Reactor Vessel Head is bolted. Either PORV has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator < 50 F above the RCS cold leg temperature, or (2) the start of a charging pump ar.d its injection into a water solid RCS.

83/4 4-11 1210 263

~ .

u:3 c n : .s.. . , - q.uxt.

CESIG'l .?RE55URE AND TEBSERATURE

2.2 The reac:cr contair. ment building is designed and shall be main-tained fcr a maximum ir. ;ernal pressure of 45 psig and a temcerature of penac.

mwU -

Si3 REACTOR CCRE

=v. :_ t_ A 5 2 :.v.a

. .. L I:_ s 5.3.1 The reactor core shall contain 157 fuel assem lies with eacn fuel assembly containing 254 fuel rods clad with Zircalcy -4 Each fuel rod shall have = ncminal active fuel lencth of 144 incnes and contain a maximum total weight of 1730 grams uranium. The initial . care leading shall have a maximum 'richment of 3.2 weight percent U-235. Reload fuel shall be similar in physical design to the initial ccre loading and snail have a maximum enrichment of 3.5 weight :ercen: U-235.

i .r_ ;7:.n_ .:~n n. .: q : r_ 5 3 'u : c_ __ . ._

5.2.2 The reac::r core shall contain 48 full length '

c:n:rci red assemblies. The full length control rod assemblies shall contain a nominal 142 inches o' abscreer ma erial.

. The nominal values of absorber raterial shall be 50 percent silver,15 percent indium and 5 percent cadmium All control rods shall be clad with stainless steel tucing.

5.4 REACTCR CCCLMIT SYSTEM g -e 3t . n.n :.___a_ :.::; r- e - a- n,t. i_...:..c.o :s t i g o. .e.

5.4.1 The reactor coolant system is designed and shall be maintained:

?00R ORDAL 121oL64 i .. .is, .,... i .n,.. .. .. .,6, - L, ,I . I i i :-,

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p ult E 3 3 2

!l =e REALY0il h1.' sisit'll IllSTRUMEllTATieft RESPollSE TIMES e

f $

x

. h RESPO!1SE TIME p g FU'lCTI0flAL UtlIT_

i 1.

Manual Reacior Trip fl0T APPLICABLE h $ 1.

-i 1 0 5 seconds *

2. Power Range, Heutron Flux

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. ;

3. Power Range,lieutron Flux,

[ fl0T APPLICADLE it' 'i Positive Rate Ih E 4. Power Range,iteutron Flux, liigh llegative Rate 1 0.5 seconds

o t u

't fl0T APPLICADLE D 5. Intermediate Range, Neutron Flux

[lr y Source Range,lieutron Flux 110T APPLICABLE

[ g 6. 4.0 Y 7. Overtemperature AT 1 f> 0' seconds *

'

NOT APPLICABLE k 8. Overpower AT .

s < 2.0 seconds O 9. Pressurizer Pressure- Low

$' 10. Pressurizer Pressure--!!igh 1 2 0 seconds

% fl0T APPLICABLE Ji !1. Pressurizer Water Level--liigh

~

o 2 lieutron detectors are exempt from response time testing. Response of the neutron flux signal 1 ~

portion of the channel time shall be measured from detector output or input of first electronic 8 N component in channel. ,

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2. &

3

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ML19256E007

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