Text

Forwards Background Info for Review of FSAR for Philippine AEC
	ML20244B557
Person / Time
Issue date:	10/25/1983
From:	Berkow H; NRC
To:	Eisenhut; NRC
Shared Package
ML20244B550	List: ML20244B546; ML20244B557; ML20244B567; ML20244B582; ML20244B621; ML20244B625; ML20244B629; ML20244B645; ML20244B662; ML20244B675; ML20244B681; ML20244B693; ML20244B695;
References
	FOIA-89-99 NUDOCS 8904190268
	Download: ML20244B557 (72)
	v • d • e

- _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ - _ _

se .j UNITED STATES 5

NUCLEAR REGULATORY COMMISSION i

%,,, / WASHINGTON, D.C. 20666 October 25, 1983 i-Darrell Eisenhut:

As you might be aware, Harold has agreed in principle to assist the Philippine AEC in ,

reviewing their FSAR for PNPP-2. The ]

attached documentation provides some back-ground. Most or all of the review specialties will come from DSI but we need a PM to

- )

coordinate our effort and to provide a single interface with the 10 or so visitors. l 1

If you agree with Roger's note will you please designate a PM to work with DSI in p developing an approach. The visitors had wanted to start the effort in mid-October; we put them off until we are better prepared to handle them.

Please keep me or Melanie Garver infonned of progress.

erb Berkow

Attachment:

14 As stated cc: R. Mattson J. Funches M. Garver li.

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8904190268 890411 PDR FOIA POTTSCHM89-9o PDRE

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l' Attachment 1 to PL-NPC/PAEct Item 15' -

Entries'in Table 3.3-11 pages 16.3/4.3-62 thru 16.3/4.3-62E will be changed from all to .the spanific number of instruments.

Item 23 -

' revised Attach,$d affecte page 16.3/4.6A-12 will be' to ' correct paragra ph 3.6.1. 6. Action-

. statement and additional paragraph 4.6.1.6.3 for. Surveillance Requirements will'be added as shown in attached affected page.

Item 26 -

Paragraph 4.8.2.3.b'on page 16.3/4.8-18 as previously written implied that the test outlined was to be conducted onl battery discharge or overcharge.y af terpara This a '

graph was revised to clearly indicate that the test are to be performed at least once per 92 days regardless of a batt charge or overcharge occurrence.ery Wedis-con-i !

clude appropriate that the Surveillance Requirements is as currently written.

For Items 3, 7, 10, 25, 27 and 37 and resolution -will be provided by February 1985.these are under review t -

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NSD FCO +.,

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CONTAINMEtiT SYSTElis CONTAINMENT VENTILAT10ft SYSTEM l

l LIMITING CONDITION FOR OPERAT10tl 3.6.1.6 The reactor building purge supply ud exhaust isolation valves q g ,

h:ll b; :ksed.

mg be opa Sv- u p % g o l4,e.g.s pr nedg APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

)

With one reactor building purge suppb . ._,

rohws Pw

...a exhaust is. nation valves j i

(

.Cu gmefose dpen c the open valve (s) within'ss es da dno.m h -be in at lust HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in C0Lu s.a>TDOWfi within i.he following l 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . !

SURVEILLAllCE REQUIREMENTS ,, j 4.6.1.6.1 The reactor building purge supply and exhaust isolation valves 7 ,

shall be verified to be: '

a. Closed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . -

b. Sealed closed at least once p... .

c.ijs . o 4.6.1.6.2 At least once per 6 months on a 5TAGGERED TEST BASIS, each sealed closed reactor. building purge supply and exhaust isolation valve shall be demonstrated OPERABLE by verifyiilg ihat the measured leakage rate is less than or equal to (0.05) L,.

4 4 . ) . c. 3 OeA e r min e.

i reache budch3 pu 4hci num bee c{ hwn v> hich e c. L. ,

i a"d P e & ~ re.ta b n vn/ves have beca opea m v: ll3 n ac.

c e. y o w e n e . h a L. Q c qe:~km A . 6 \ . G . 2- al Lec. d o n ec ev \

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3-101284 16.3/4.6A.- 3P/P/ll27P:7

/, mend. No. 2, 9/83 {

Amend. No. 6, 10/84 L___--___-_-___-_-__------------- - ]

. g- ,

l.3 Attachment 1 to PL-NPC/PAEC- O'70'?

l Item 25 - Surveillance requirements for charcoal and HEPA filter systems are revised per USNRC Generic Letter 83-13 as noted on attached revised pages 16.3/4.6A-30, 16.3/4.6A-31,16.3/4.7-17,16.3/4.7-18,16.3/4.7-19, L 16.3/4.8-17, 16.3/4.9-18, and 16.3/4.9-19.

I Itsn 27 - : FSAR Sections 3.8.1.1 and 4.8.1.1 are amended to address Generic Letter 84-15. Affected pages 16.3/4.8-1 to 16.3/4.8-5 and 16.3/4.8-11 with new Table 4.8-1 A are attached, item 37 - The attached revised pages; 16.3/4.7.15,16.3/4.7-16,.

16.3/4.7-17 and 16.3/4.7-41 are amended to reflect the as-built plant of PNPP-1

' 1) On the subject of ultimate heat' sink level, attached FSAR nage 16.3/4.7-15 changes the defined minimum water level .

2)' Attached revised pages 16.3/4.7-16 and -17 reflect actions related to the MCR air condi-tioning systems.

3). Attached revised page 16.3/4.7 reflect resolution of comment concerning low pressure C02 systems. The installed-C02-is high pressure only.

For items 3, 7, and 10, these are under review and resolution will be provided by the first week of March-1985.

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- _ _ _ _ _ _ _ _ _ _ _ __ .___m ________.-_____________.______._._____.________________m_. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _

4 3/4.8 ELECTRICAL POWER SYSTEMS l 3/4.8.1 AC SOURCES

, OPERATING-LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following AC electrical power sources shall be OPERABLE:

a. Two physically independent circuits between the offsite transmis-sion network and the onsite Class 1E distribution system, and

b. Two separate and independent diesel generators, each with:

i. Separate day fuel tank containing a minimum volume of 3 2,660 gallons of fuel, O

g' 2. A separate fuel storage system containing a minimum volume of 60,000 gallons of fuel, and N

3. A separate fuel transfer pump.

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

ACTION:

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a. With +4e er an offsite circuit e dic:;? ;;c.;ci... of the above :

required AC electrical power sources inoperable, demonstrate the offsNe OPERABILITY of the remaining AC 3 sources by performing Surveil-lance Requirement / 4.8.1.1.1.a -f '.S.!.?.2.: d within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

. andatleastonceper8hoursthereafterp3 restore at least two ,

offsite circuits and two diesel generators to OPERABLE status M !

l ,ab sune; no.ca ,e t a e. m + 4.E.l.1.2.*.4 .

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2-012384 16.3/4.8-1 3269/0981P:7 Amend. No. 3, 1/84 1.____ _. ._._.__. _ _ _ J

ELECTRICAL POWER SYSTEMS 1

ACTION: (continued) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

a.

b. With r e-:'f:it: circuit c.nd n: diesel generator of the'above required AC electrical power sources inoperable +, demonstrate the i i

affs s'ff-OPERABILITY of the - :' ' ; AC sources 3 by performing Surveil- l

~ . . _ _ .

lance Requirements 4.8.1.1.1.a =d ' ^ f 'l_;.4 within I hour d in is t s.< -< ^*#s

( ys s ,a as-se njas- and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafterg)regt, ore gt h:,:t r M

' a 4.y , s. j, t , u 4 UINIlh:ur;orbe wi#uta 2s Nu rsp/ the 'r;: ..;1e ::rce to OPERABLE status wi Q in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 4 +s and e u ~ s> e <in COLD

< /g uaSHUT-

<<.s DOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ". : tere :t le::t t::e 0.f:ite

{%!At, 'l,'ft'fl1 AN'!! 22?T lE?o'k'We%'559,1lid '*

s kch:dj%R24%WOWWR5'NMd(ff . ""' ;

O\ ' pile 4,3 - z u // s L4Ti&E * * "' "" "' "~ 'N wi tli i n the i Q S.MD9Y "it4iin the next S heur: =d ' a COLD S"'JT00'-

fel1eua; 20 Seur>.

c. With ena d t :1 s nciaLor e " nu p er a'v i e in edditiw Lu (a)vi (irb above. ver_ify that:

equired syst es, :ebrystems, trains, re=reaea p h f ces that depend on the remaining OPERABL sei genera-g urce of emergency power a so OPERABLE, and tor as

$ jef (2) When in MODE 1, 2, or he steam-driven auxiliary feed I pump is OPERABLE.

If these c ' itions are not satisfied within 2 i;c be in at OWN leas T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD S l

ithin the falley 9; 30 heget.

4 O 3218/0638P:7 1-072282 16.3/4.8-2

- - - - _ _ __ _ [

~

I' ELECTRICAL POWER SYSTEMS ACTION: (continued)

d. With two of the above required offsite AC circuits inoperable, demonstrate the OPERABILITY of two diesel generators by perform-ing Surveillance Requirement 4.8.1.1.2.a.4 within hour 5aed-+t ;

ic;;t cr.ce per S hour; theieafien, unless the diesel generators are already operating; restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . With only one'offsite i source restored, restore at least two offsite circuits to OPER-ABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

e. With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite AC circuits by per-forming Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months er be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Restore at least two diesel generators to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of j initial loss er be in et least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and.in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

NWh. .,

SURVEILLANCE REQUIREMENTS

\ ~A I

4.8.1.1.1 Each of the above required independent circuits between the off-l

site transmission network and the ensite Class 1E distribution system shall be: -

0 1-072282 16.3/4.8-3 3218/0638P:7

l '

ELECTRICAL POWER SYSTEMS I

1' SURVEILLANCE REQUIREMENTS (continued)

a. Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability, and 1

b. Demonstrated OPERABLE at least once per 18 months during shutdown by transferring (manually and automatically) unit power supply from the normal circuit to the alternate circuit.

4.8.1.1.2 Each diesel generator sh.all be demonstrated OPERABLE:

a. In accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST BASIS by:

1. Verifying the fuel level in the day tank, 9 2. Verifying the fuel level in the fuel storage tank,

3. Verifying the fuel transfer pump' starts and transfers fuel from the storage system to the day and engine-mounted tank,

4. Verifying the diesel starts from ambient condition and accelerates to at least 900 rpm in less than or equal to '

10 seconds. The generator voltage and frequency shall be 6,900 + 690 volts and 60 + 1.2 Hz within 10 seconds after 3 the start signal. The diesel generator shall be started for this test by using one of the following signals;H th :t:rtup a . ;;;h signal v;r!'fid :t-1 ::t once p. g:r 6 -(

h p <- s --- -ny*

b_....,_ u- --s.,,, ._ me - u s.s-9 ~ > p_. s n

+ luce et " A " ,

3-101284 16.3/4.8-4 3272/ll45P:7 Amend. No. 3, 1/84 '

Amend. No. 6, 10/84

ELECTRICAL POWER SYSTEMS SURVEllt.ANCE REQUIREMENTS (continued) a) Manual. ,

b) Simulated loss of offsite power by itself.

c) Simulated loss of offsite power in conjunction with an ESF actuation test signal.

d)- An ESF actuation test signal by itself.

5. Verifying the generator is synchronized, loaded to greater i

than or equal to 4400 kW in less than or equal to l3 60 seconds $ and operates for greater than or equal to 60 minutes, J

6. Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.-

b. At least once per 31 days and after each operation of the diesel where the period of operation was greater than or equal to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months by checking for and removing accumulated water from the fuel day 3 i tanks.

c. At least once per 92 days (or once per 31 days if the ground-water table is equal to or higher than the bottom of the fuel oil 3 tanks) by checking for and removing accumulated water from the fuel oil storage tanks; ,

O 2-012384 16.3/4.8-5 3269/0981P:7 Amend. No. 3, 1/84 h __ _ -____ . _ _ _ _ _ _ _

/7ewc @ f) a.3/+. 9 -9

The ches el ege,uers b sfa rf (so sec.)from gm hie,J Wifim.r q

%Il lx ge.vQweel d lea sl coce per 19 A- elays tw O cse su.vvelll amc0 tesh . /9/l oMe ey oe t s.t v +, t- f4e fv.#ere.

0$ % {.5 Cu.r ve;lla n,ce heshwg in9 be gye ce cled .%

eq h e fveI O e peviocl twtdlov ollek @ vin af Qrdcedu.ve 3.

v 6 c 4 r>1 m e n cfe 4 by Y rVl% n htc$ Mr6V .so 'fkAl Meckr1Mc 9f s4es, nvd m a fle .I s e.sel eye u d o; 4 5 4

. Jn/cEv 4 @ h 1 (,. 3/4- , 8 - 2. . _, . . , .

c. Wi.th one offsite circuit and one' diesel generator-o# the above required A.C. electrical powe.r sources inoperable, demonstrate

. _ . . _ . the OPERABILITY of the remaining A.C. offsite source by _

performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter and Surveillance Requirement 4.8.1.1.2.a.4 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; restore at least one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in -

- COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With the diesel generator restored to OPERABLE status, follow Action Statement

. a. With'th'e offsite circuit restored to OPERABLE status, follow Act. ion Statement b.

'J 4 s s c.T @J lI-. 3/4.9-3

A diesel generator shall.be considered to be inoperable from the time of failure until it satisfies the requirements of Surveillance Requirement 4.8.1.1.2.4 ELECTRIC POWER SYSTEMS .

lakt-

- The maximum t e that an individual diesel generator may be inoperable ( ) shall be established by the licensee based on the 7

l manufacttirer's recommendations and previous maintenance and repair experience. Every reasonable effort shall be made to restore individual diesel generators to operable status within that time period (# . Every reasonable effort shall be interpreted to mean .

that ding iosis and repairs are to begin immediately and are to continue ' interrupted until the diesel generator is declared operablego orderly retreat to cold shutdown is initiated.

"'The maximum total cumulative time that the diesel generators of the onsite emergency AC power system may be in the INOPERABLE status in a given year shall be proposed by the licensee.

. . ?. .. ...

1 c- -

a

. I J.

TABLE 4.8-1

' DIESEL GENERATOR TEST SCHEDULE NLMBER OF FAILURES IN LAST #00 VALID TESTS

TEST FREQUENCY 20 At least once per 31 days 11

-2 At h e;t Once pe. 14 deys-3 At least once per 7 days #

d4 At ice;t or. c per 3 days j O

l 1

l

,,,,,, se r o.f A sfs a nd /*i l~'*s

Criteria for determining number of 'f ilures and number of valid tests shall be in accordance with Regulatory P ition C.2.e of Regulatory Guide 1.108, .

Revision 1, August 1977, where theY':.;t 100 t;;t: :re determined on,a per l

! jf,,, t y,, ,,a* rut'- r u M t basis. For the purposes of this test schedule, only valid l

tests conducted after.t,be OL issuance date shall be included in the compu-l tation of the "last WHF valid tests." E*L+ry Ste thh teet ;;h th- 0h:11

--a .n>A__ .+ + u. E-, ,.

j3 fest fe a nue s h e // be o.,a i n f* **e e d u n t nV t a ve rs of der" See u t*>

l*'f ,

gy free de- ds have bez n /w fe e ~ e J ond he n~=*" f* I I" ' " '" '

O'~ /a s + t o en lo'd d e e< * *s d.s Iso es has n re du es d to o *' e e r /t15.

3218/0638P:7 1-072282 16.3/4.8-11 l

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TABLE 4,8-f ADDITI0f1AL RELIABILITY ACTIO!15 No. of failures No of failures >

in last 20 in last 100 '

valid' test valid tests Action 3' 6 Within 14 days prepare and f * " :

l maintain a report for 4 tite audit !~

describing the diesel generator -

reliability improvement program ' ;

implemented at the site.

i

, Minimum requirements for the report are indicated in Attachment 1 to this table.

5 11 Declare the diesel generator .

inoperable. Perform a requali-

- fication test program for the

.affected diesel generator.

Requalification test program requirements are indicated in Attachment 2 to this table.

9 4

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ATTACH 4Etli 1 TO T/.BLE 4.8-E .

J' REPORTING REQUIRE 14Elli PA Gc As e ninicum the Reliability Improvement Program report for IEC audit shall include:

a) 6 summary of cil'tes;c (valid end invalid) that occurred within the tire period over which'the last 20/100 valid tests were performed b) cualysis of failure: nnd determination of root causes of failures c) evtluation of each cd the rcccamendations of liUREG/CR-0660, "Enhan.:eitent of Onsite Emergency Diesel Generator Reliability in Opt.reting r.esctors," with respect to their application to the P1: n. i d) identification of all Sctions taken or to be taken to 1)' correct

the rco. n eses of fciiures defined in b) r.bove end 2) achieve a V gener:1 improvement of diesel generator reliability e) the sct.edale'for implementation qf each iction from d) above ( .

f) t.n assest.mr.nt of the exit. ting re ncbility of cicctric power to engineered Lefcty-ftstere equipment. i On:e 6 licensee has prepu ed cnd taintain an initial report detailing the diesel err.erator rditb.'i y tir..prevement progrLm at his site, as enfir.tC eb:.vc, the licensec nt :d prepare only e supplenentcl icport withia 14 days after each it.ilure during a valid deucnd for so long Es the (.ffLctcd dierti gcr. Orate.r unit continutt to violate the criteric e '(3/S or 6/}LG) for the relit.bility improvennt program rttedial action, i b: w ple m.1 1 repr.rt need or1; rp6e.n the fcilure/ den!.r.d history for th ficci.ed ciesel genertu;' nit sina the itst report for thr.t diesel gererr.t:r. Thc. supplcr.ent:1 -tr rt thh11 6150 present an analysis of th(

i,ilurr (s) t.iih r r cci ci..n d crninetion, if. rest sbit., tr.d shall deli:. .Lc any.further prt.cederrl i hir0.tre or op: 1tionn' chtnges to be incorpri.ttd into the site diesel'generstar ir.prov rent

. pro;.ren end the sched'.:le f or impin.cntr.tica cf thest. changer.

, 4 tp b' b.l .g ap .I 5 l s .* .' q.

. h ' .1 e 4 gC h';t *: tor I Elithility.

l _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

4'-

M

.. . f i

- =

)

..' l i' /A i ATTAC1111E!1T 2 TO TABLE 4.8-f DIESEL GENERATOR RE00ALIFICAT10N PY0GRAli_ .

l (1) ' Perform within 30 seven days of.consecutive diesel generator successful demands being restored to without opereblea failure status and fourteen consecutive successful demands without a failure within 75 days of diesel generator of being restored to operabic status.

(2) If a failure occurs during the first seven tests in the requalification test program, perfonn seven successful demands without an additional failure within 30 day's of diesel generator of being restored to operable status.and fourteen consecutive successful demands without a failure within 75 days of being restcred to oparcble status.

(3) If a fcilure occurs during the second seven tests (tests 8 through

14) of (1) above, perform fourteen consecutive successful demands without an additional failure within 75 days of the failure which occurred during.the requalificaticn testing.

(4) Following the second f ailure during the requalification test

.} program, be in'at'least liOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

' .and COLD SHUT 00',M within the foljowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

(5) During requalificatien. test.ing the diesel generator should not be tested n. ore frequently than at 24-hour intervels.

After a diesel generator has been successfully requalified, subtequent repected requalification tests will not he required for that diuel generctor under the folicuing conditions:

(a) The num.ber of failures in ihe last 20 valid demands is less than

. 5.

v (b) The number of failures in the inst 100 valid demands is less then

. 11.

(c) In t!.e cvent thi:t following successful requ61ificction of a diece) generttor, the number of fciiures is still in encess of the rersdial action criterii. (a cnd/cr b rhove) the follo,rire n ceptior will,be c110wed until the diesel generator is no lonc6r in violation of the remedici ection criteriri (a and/or b abovc).

isequalification testing vill but he recuired providcd thtt af tcr ccch vilid dt. r,6 ii :. rr a , cf it.ilures in t he icst 20 2.W/nr 103 s ciid r

L'; '"

'. I ~.t r V C (l ' ! t. } 0 '-

T r . i' . . " if rn 1N (2r i n V i D l i '. r. '. i IL '( .. " i i Liibt. C r i t s '. i s. O b 7. 0 'U [r'..'isidi' of l

l that.e crit;ria tier.e viil prchil, l

w_----___-_ _ _ _ _ _ _ _ _

j[

k.

(

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (continued) 1.

Gwne+e* Hen

M h rsst lu LD Verifying that the RBANPCS satisfies the in-placenesung et s eas ***= e.es 7 6L acceptance criteria 3 and uses the test p w,w. a r#ww.caget.Re tory Positions C.S.a., C.S.c., and C.'5.d of Regulatory Guide 1.52, Revision 1 July 1976, and the system flow rate l 3

is 3,000 cfm (5,097m/hr)+10%. ,

2. Verifying within 31 days after removal that a laboratory !

t analysis of a representative carbon sample obtained in i accordance with Regulatory Position C.6.b,*ee Regulatory Guide 1.52, Revision 1 July 1976, meets the laboratory testing criteria of Regulatory Position C.'6.'a of Regulatory ]

Guide 1.52, Revision 1, July 1976 fer 4 m a+hyl Ndide .

pe.,s+mwe,s of less %en l */e, 3

( i

3. Verifying a system flow rate of 3,000 cfm (5,097 m3 /hr) l

+;10% during system operation when tested'in accordance with ANSI N510-1975.

- c. Af ter every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operatiogby veri-fying within 31 days after removal, that a laboratory analysis of -

a representative carbon sample obtained in accordanc'e with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1

. July 1976, meets the laboratory testing criteria of R.egulatory Position C.6.a of Regulatory Guide 1.52, Revision 1 July 1976, J 4ee s w k9 teto'ds fee.e.+m % e4 less +s.s., $%, .

d. At least once per 18 months by:

1-072282 16.3/4.6A-30 3218/0620P:7 i

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (continued)

1. Verifying that the pressure' drop across the combined HEPA filters and charcoal absorber banks is < 6 inches Water Gua90 while operating the system at a flow rate of 3

3,000 cfm (5,097 m /hr) i 10%.

2. Verifying that the system starts on a Safety Injection Test Signal and on an Annulus High Pressure Test Signal.

3. Verifying that each system produces a negative. pressure of 2,6.5 mm of H O in the annulus within 1 minute after a 2

start signal.

4. Verifying that the heaters dissipate 20 kW when tested in accordance with ANSI N510-1975.

e. After each complete or partial replacement of a HEPA filter bank by verifyin m+ ts s;* + ,. t a . % pe .. +. . a m e d by--^ :- ' ?R - 3p;tje m.g te sn splafwasyc,kthatthe,HEPAfilterban

,<4 s.. .or -

' -.---.-+n

a. o 6ne!

oa f sn : :. w4./e r s. sf +P e d ' ; , %.::: in accordance N510 fee1975 while operating the system at a flow rate of 3

3 3,000 cfm (5,097 m /hr) i 10%. ,

I

f. After each complete or partial replacement of a charcoal adsorber ban by verifying that the charcoal absorbers remov. wov so.4A'es e

t uY W --- Wi* .. .

fs(W .*hw sofb u ys_s_s.jen usys,f,*s9l,* ,

n,~g Ren'~$

<*. +*s e:

,,..vgu..__ . . , _ . _ _ _ . _ . _ .

~ '

(for s Miyonant] Na"+ N E 9.i f ' ;1: n in accordance with ANSI N550-1975 i

4 6 4 e m eben N' }w(hileoperatingthesystemataflowrateof3,000cfm 3

5',097m/hr)+10%*

Gye.nt test ys

(

?? 05! ;;pif: d' 'A

- : f'it 7 :"':': y ' ??! 4: ::; ;;,,J in ine S afa+y an='y'"' ; 00% , l,,,, . T M 6e, of f ;s ; ..y ;f ??" :. onumeo.

1-072282 16.3/4.6A-31 3218/0620P:7

[, ,

s I PLANT SYSTEMS SURVEILLANCE REQUIREMENTS-4.7.6 Each main control room charcoal cleanup system fan and plenum shall '6 be demonstrated OPERABLE: -

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control roc.n air temperature is'less than or equal to 26.7'C (80*F).

b. At least once per 31 days on a STAGGERED TEST BASIS by initiat-ing, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

c. At least once per 18 months or: (1) after any structural main-

, tenance on the HEPA filter or charcoal adsorber housings; or

! (2) following painting, fire, or chemical release in any venti-lation zone consnunicating with the system by:

1. Verifying that with the system operating at a flow rate of 28,350 cfm i 10 percent and exhausting through the HEPA filters and charcoal adsorbers, the total bypass flow of the system to the facility vent, including leakage through j the syste> diverting valves, is less than or equal to 1 percent when the system is tested by admitting cold D0P at the system intake. (Forsystemswithdivertingvalves.)

7. Verifying that the cleanup sp' tem satisfies the in-place ec=%tN

. ,g t,3p m testingacceptancecrYtNaand"useIthetestprocedI[r'7["

3 e ;

le * **34 Regulatory Positions C.S.a. C.S.c. and C.S.d of Regulatory Guide 1.52 Revision 1 July 1976, and the system flow rate j is 28,350 cfm i 10 percent. )

I l

2-1012M 16.3/4.7-17 3272/1143P:7 l Amend. No. 6,10/84

, PLANT SYSTEMS .

o j

SURVEILLANCE REQUIREMENTS (continued) ;

3. Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Posi1iion C.6.b of Regu'latory Guide 1.52, Revision 1, July 1976, meets the laboratory testing criter,ia of Regulatory Position C.6.a of Regulatory ,

Guide 1.52, Revision 1. July' 1976, f*r * **Ds I /*dids

I f e n e tra t,'an e f le gg W. J %,

4. Verifying a system flow rate of 28,350 cfm 1 10 percent during system operation when tested in accordance with ANSI N510-1975.

d. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of. charcoal adsorber operation,by verify-ing within 31 dry: af ter removal, that a' laboratory analysis of i

a representative carb'on sample obtained in accordance with Regu-latory Position C.6.b of Regulatory Guid'e 1.52, Revision 1, July 1976, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, . Revision 1, July 1976 3

, 4ee

mesu s todits tenet renen of I<u %n s yo, j e. At least once per.18 months by:

~

. 1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is 'less than 6 inches Water. Gauge (W.G.) while operating the system at a flow rate of 28,350 cfm 110 percent. *

2. Verifying that on a control room isolation test signal, the system automatically switches into a recirculation mode of cperation with flow through the HEPA filters and charcoal

,. adsorber banks.

1-072282 16.3/4.7-18

3218/0628P:7

.. 1 1

l

\

. PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (continued) f.

After each complete or partial' replacement of an HEPA filter bank by verifying that the HEPA filter banks.rtsstu +, in .

*

b!,* 'ln '" *L'I

NK%* *!*?!* "M **'%'/* -^' '* r ;.::t:-

, o <e ten th:n e.+essie .

_..,r-- -

- -- -<- "" ""E" 6s --}'+ !.h3 * **%

fee A OOP Pebtsere el- --

W in accordance with ANSI N510-197gwhile operating the system at a flow rate of 28,350 cfm f.10 percent.

\

g.

After each complete or partial replacement of a charcoal As adsorber bank by verifying that the charcoal adsorber/ pem w 4

b. t%f,"+ d! _ .* . L"

. , . *t*'*A*

. . . . .A*A* _ . $C*?i*'* * *A ? V4!U*S Wt *;b}k"! S

.^ , i i

[* Sept

v12, c ,it.r. *4_ */ T*J.th*1

. . . . . . . . , _ . _ .. ,., . . . . . . . . , a.*!N

. . . . . *_ _.. 3 ,. ,,... in_

accordance with ANSI N510-1975 while operating the system at a flow rate of 28,350 cfm + 10 percent.

for a h e /o,p nn, t bede**<eben refroyer***+

test gas i

y y y v S .::;.:1

_0^ ; ~ . ., + 4 e me .-M:t: ef ^^.^ ; r:::t ': ;;;;i; ;,1; .f.;;. ; fil;.s. e m cienc H ~' i"M

r. c. f 11 i si ef7';i;r.;; ;,f ^^ ;;,.:..t ': t :f ^^ p,y, , vf

<- th: ,;';ty ;;,;; ;,;, ; :_:; 1 , , ,;

d.

1-072282 16.3/4.7-19 3218/0628P:7

. i REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (continued)

a. At least once per 31 days on a STAGGERED TEST BASIS by initiat- I ing, from the controt room, flow through the HEPA filters and charcoal edsorbers and verifying tha't the system operates' for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters on.

b. At~1 east once per'18 months or: (1) after any structural main-tenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in ,any ventilat' ion zone communicating with the system by:

Verifying that with the system operating at.a flow rate of 1.

30,000 cfm + 10 percent and exhausting at a flow rate of 15,000 cfm i 10' percent through each set of HEPA filters and charcoal adsorbers,'the total bypass flow of the system to the f acility vent, including leakage through the system diverting valves, is less than or equal 'to 1 percent when the system is tested by admitting cold 00P at the system

~

intake. (forsystemswithdivertingvalves.)

2. Verifying that the cleanup system satisfies the in-place P'a*NS" anIuseNhetestproceMr* #"

w g, b pp testingacceptancecriTer Regulatory Positions C.5.a C.5.c. and C.S.d of Regulatory Guide 1.52, Revision 1, July 1976, and the system flow rate is 30,000 cfm 110 percent. - -

l

3. Verifying within 31 days af ter removal that a laboratory l analysis of a representative carbon sample obtained in i accordance with Regulatory Position C.6.b of Regulatory 1 Guide 1.52, Revision 1. July 1976, meets the laboratory l 1-072282 16.3/4.9-17 3218/0629P:7

i ,

t REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (continued) testing criteri,a of Regulatory Position C.6.a of Regulatory Guide 1.52' Rev'ision 1 July 1976, fee a ms4%/ *ed.'de fenstatsw of less 48 a 1%

4. Verifying a system flow rate of 15,000 cfm + 10 percent per exhaust filtpr plenum during system operation when tested in accordance with ANSI N510-1975.

1

c. After.every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation j by verify-ing within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regu-latory Position C.6.b of Reguintory Guide 1.52 Revision 1

/

July 1976, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52. Revision 1. July 1976 3

fee a me 4 %I iod:de (eneMtter, .6 teu h ., t %

d. At least once per 18 months by:

1. Verifying that the pressure drop across the combined HEFA filters and charcoal adsorber banks is less than 6-inches Water Gauge while operating the system at a flow rate of 15,000 cfm + 10 percent through each filter plenum.

~

2. Verifying that on a safety injection test signal, the l2 system automatically starts (unless already operating) and 4

directs its exhaust flow through the HEPA filters and charcoal adsorber banks.

1

3. Verifying that the system maintains the spent fuel storage pool area at a negative pressure of greater than or equal l to 1/8 inch water gauge relative to the outside atmo-sphere during system operation. j l

2-093083 16.3/4.9-18 3268/0948P:7 Amend. No. 2, 9/83

{

f

- --- . _ _ _ . 6.._._..._._ _ .

i REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (continued)

4. Verifying that the heaters dissipate 52 kW i 5 percent b (VA 449.HTR), 35' kW i 5 percent (VA 448 HTR), when tested in accordance with ANSI H510-19'75. 2,

e. After each complete or partial replacement of an HEPA filter bank by verifyin "that the HEPA filter ban #*!Mi' Mid@"- -

M 'tb'*3?" 1?? 3$5?!LP' /*'s

. , , - . %"#eh 9e*,.L'l1**f.

.g*A*'L.'.s A".;t*

-p?rr ,in accordance with ANSI H5101975 whileopeElfn,.g the system at a flow rate of 15,000 cfm i 10 percent through each filter plenum.

f. After each complete or partial replacement of a charcoal he n k adsorber bank b ramoxe.

'*!!!& Ak' /*y verifying that the charcoal adsorberp3

'ff*!f 2"t!W*? *"A MNff%41O ksBy ' .

ij E 3 % .Y 5 f it E#.Y8K d art g f{*[;]{;"] $7, g ;

3, accordance with ANSI N510-1975 while operating the system at a flow rate of 15,000 cfm i 10 reent through each filter pienum.

Ja s hetoya sv.d e A y o'rees o b* **

f~c frif*r*** 0 Y"t Y*A __

r 1

V%% ^vw'

A-<.,w.e 7:t cf oo CC ;:rced i. .yy'icopis wnen a T i s ter eiisu senwy 4 Qreant te n:rd f n th n?;ti onei.r;;;, ; ~ s' t ;f00pr:rt l B =rs "<:eb!: tr f f ?tr ;fff;i=:; cf 60 pa"^at i; ;;.s;de 1 3-101284 16.3/4.9-19 3272/1148P:7 l Amend. No. 2, 9/83 l Amend. No. 6,10/84 :

i

.< .Page -l of 4 --

9-Y e ie '

ATTACTSENT 1 to _

Item 1 -

To conform to the PAEC reco: Tended changes, pages16.1-7, ;

-16.6-8,.16.6-12, 16.6-15,~16.6-19, 16.6-22,~16.6-27 and ..

j 16.6-29 are being revised as shown in the attached affected '

pages to be consistent with the issuance of-.10CFR 50.73.

Material on pages 16.6-23 through 16.6-26 are deleted.

A

Item 2 -

Defirtition of shn a m mrcin is being revised to be consistent with 1.'UPm-0452. -

1 Item 4 -

Tables 2.2-1 and 4.3-1 are beim revised as indicated in -

attached affected cages 16.2-7,.16.2-14, 16.2-15, 16.2-16 ,

and 16.3/4.3-11. E mther, pages 16.3/3.3-12 and 13 are being revised consistent with the PAEC Ccmrent.

Item 5 -

Action state:mnts for paragraphs 3.1.1.1 and 3.1.1.2, pages.

16.3/4.1.1.and 16.3/4.1-3 are being revised for-equivalent j boration rates, j

i i

Item 6 -

This is to confirm that the SI ptzrps are capable of being lined up to deliver water from the PWST to PCS. Shutoff head of these pu:tos is approximately 2,200 psi, which

allows the ptrrps to discharge to 'the BCS at a slightly lower than ncminal pressure. Thus, specification 3.1.2.2 on page 16.3/4.1-11 should temain as written.

Item 8 -

Applicable specification referring to PWST freezing point.

will be deleted. Attached affected eages 16.3/4.1-16, j 16.3/4.1-17,-16.3/4.1-18 and 16.3/4.5-14 are being !

corrected.

{

1

! Item 9 -

Action statermnts under paragraph 3.1.3.1, page 16.3/4.1-20 are being revised in line with the recommended changes associated with Shutdcwn, Margin.

L Item 11 - Table 3.3-4 notations on attachal affected page 16.1/4.3-28

! will be revised to delete contents of tbre 6.

Item 12 -

Attcched af fected Table 3.3-6 is being mvtsd to dele te

' entries under ntribers 1.c,1.d. ' #, . 1. :: , r.d 1. h .

r; b

)

ly!

.Page 2_ of 4_

9 l

Item 13 -

Action 30 of Table 3.3-6 is being revised as shown in attached affected page 16.3/4'.3-42.

i 5 l

Item 14 -

Tables 3.3-9 hnd 4.3-6 include all instruments which are provided and needed to monitor reactor shutdoan from the Retrote Panels. Likewise, Tables 3.3-10 and 4.3-7 include these instruments. Therefore, no changes are l . required.

Item 16 -

Attached affected page 16.3/4.3-64, item (a) will be revised to reflect surveillance once per 31 days.

Item 17 -

This is to confirm that 3.4.1.2.b is correct and therefore no change is required. 'Ihe minimum safety analysis require-rrent for bbde 3 is that at least one loop be operating, i A second operable loop satisfies single failure criteria.

Item 18 -

' Attached affected pages 16.3/4.4-20 and 16.3/4.4-21 are i being revised to correct paragraphs 3.4.6.1(a) and '

4.4.6.l(a). ,

Item 19 -

The assunption of'one charging pumo which is manually operated to deliver additional flow to the PCs is to l

' conservatively Iraximize doses. and do not explicitely '

model operator actions or response of the plant. In >

actuality, in the event; that a charging pump is running and an SI signal occurs concurrent with a blackout condition (which is the assu:qation considered in the SGTR accident presented in the FSAR), the charging pump will trip and is locked-out.

Thus, we see no basis for making a change in 3.4.6.2 and 4.4.6.2 of the Plant: Technical Specifications.

e Item 20 -

The maximum Rh3T volute in spray and final containment sump pH was 1001, of tank volune. In the determination of the mininum post-accident pH limit, a INST volu:re at the i

tank overficw elevation to the tank outlet elevation was assuned for conservatism. Thus, there is no need to include in the Tech Specs a maximum volune limitation.

Item 21 -

Paragraoh 3.6.1.,2 (a) on attached affected, page 16.3/4.6A-3 1

J

) Page 3,of 4_

[* ] ,

1 is being deleted. Peferences to h in other parts of the Tech Specs are also being dele,ted. ;

l

,)

Item 22 - ILO and SR- from page 3/4.6-11d of NUPIG - 0452 are being added to the Tech Soecs.

I

{

Item 24 - Attached affected page 16.3/4.6A-19 is being revised to j periodically demonstrate flow through the entire MaOH l path.

Item-26 - As recommended, contents of Table -3.7-4a and 3.7-4b are being deleted in their entirety. Peferences to these tables in Specifications 3.7 and 4.7 are also being >

deleted.

Item 29 - The functions, composition, responsibilities and authority of the Independent Safety Engineering Group is being added in the Plant Technical Specifications.

~

Item 30 - Attached affected page 16.6-5 is being revised to include in Table 6.2-1 to note that overtire limits aoply to key traintenance personnel.

Item 31 - , Attached affected pages 16.6-13 and 16.6-14 are being revised to' change audit frequencies to once per 12 months.

Item 32. - Attached affected eage 16.6-15 is being revised to specify in 6.5.2.10.a to c that these records are forwarded to the Vice-President responsible for Nuclear Po w r.

Item 33 - Attached affected pages 16.6-15 and 16.6-19 are being revised per Generic Ietter 83-43.

Item 34 - Attached affected page 16.6-16 is being revised to include item (e) that states that critical operation of the unit shall not be resuned until authorized by PAEC.

Item 35 - Attached affected page 16.6-19 is being revised to include 6.8.4.d and e of the W - STS.

I r ,

_ _ _ . . _ - .- _ __.__..-_..m. _____ ___-_- ..___._..__m_.___2__m___ ________-__m___.:__.-___-_______m m__.--_m_ _.m.2_

i aes , -vi 4 ;

. ) ) i l ,

l i Listings of various Special Reports are being deleted from Item 36 -

pages 16.6-22 to 16.6-26.

For ite.ms 3, 7, 10, 15, 23, 25, 27, 28 and 37, these are under review and resolution will be provided by the second week of January 1985.

l e

e h

a eug a

e 4

-l

) > l

- REACTIVITY C0ilTROL SYSTEMS j

' ,'j'"

I BORATED llATER SOURCES - SHUTDOWN LIMITIllG C0flDIT10tl FOR OPERAT10!1 ;

3.1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE: ;

a. A boric acid storage system and assoc'iated heat tracing with:

3

1. A minimum contained borated water volume of 7.48 m 4 (1977 gallons),

l

2. Between 7,000 and 7,700 ppm of boron, and-

3. A minimum ::olution temperature of 18.3'C (65'F).

The refueling water storage tank with:

4, b. ,

3

1. A minimum contained borated water volume of 87 m g (23,000 gallons),

2. A minimum boron concentration of 2,000 ppm, and

3. ^-minimum soluT. ion temperature or i.ot,ust).

~

APPLICABILITY: MODES 5 and 6. ,

l ACTION:

With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

k.

2-041584 16.3/4.1-16 3270/1043P:7 Amend. No. 4, 4/84

7 lg A

)

i 1

.- REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS I i 4 i 4.1.2.5 ' The above required borated water source shall be demonstrated i OPERABLE:

a. At least once pet 7 days by:

s l

l

1. Verifying the boron concentration of the water, i

l l- 2. Verifying the contained borated water volume, and

3. Verifying the boric acid storage tank solution temperature when it is the source of borated water. '

At 1 pact nnet nar 24_.hou r e hy ver4fy4ng-the-RWST-temperature b_.

when-i tHs -the-sourca_of_horate_d water. 'l k

1-072282 16.3/4.1-17 3218/0577P:7

-) J !

1 1

T' REACTIYlTY CONTROL SYSTEl15 )

00 RATED WATER SOURCES - OPERATillG LIMITillG C0!!DITION FOR OPERAT10tl 3.1.2.6 .As a minimum, the following. borated water source (s) shall be k i

OPERABLE as required by Specification 3.1.2.2:

4

a. A boric acid storage system and at least one associated heat tracing system with:

1

1. A minimum contained borated water volume of 34.8 m3 4

(9,187 gallons),

2. Between 7,000 and 7,700 ppm of boron, and

3. A minimum solution temperature of 18.3*C (65*l),

/

s , i

b. The refueling, water storage tank with:

l

1. A minimum contained borated water volume of 20!. 9 m3 (54,420 gallons),

2. Between 2,000 and 2,100 ppm of boron, and "J . A m'inimum solution temperature of 1.6*C (3b"F)".

l2.

=

APPLICABILITY: liODES 1, 2, 3, and 4. i

. 1 ACTION:

a. With the boric acid storage system inoperable and being used as one of the'above required borated water sources, r.estore the storage system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at l

j

~

3-041584 16.3/4.1-18 3270/1044P:7 Amend. No. 2, 9/83 Amend. No. 4, 4/84

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TABLE NOTATION (i) Diesel genera' tor starting and sequence loadi.ng delays included.

(2) Diesel generator starting and sequence loading delay not included.

Offsite power available.

.(3) Air-operated valves.

RHR (4) . Diesel generator starting and sequence loading delays. included.-

pumps not included.

(5) Diesel generator starting and _ sequence loading deJays not included.

RHR-pumps not included.

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{. TABLE 3.3-6 (continued)

ACTION STATEMENTS l

ACTION 25 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, perform t.rea 1,urveys of the mon litored area with portable monitoring instrumentation at I least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . ,

ACTION 26 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION j requirements of Specification 3.4.6.1.

ACTION 27 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, coniply with the ACTION requirements of Specification 3.9.12. I

, ACTION 28 - With the number of OPERABLE channe.ls less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 29 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventila-tion system in the recirculation mode of operation.

l ACTION 30 - itith uis is . umn . syu h ed by Lie-nwis.lerCPErsAEEuduncia

. Mir'-"- Ch:anci s vr umett requ i. . .mn i, restore the inoperable l t

channel (s) to OPERABLE status within days, or be in at least j HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , n at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COL SHUTDOWN within the l

subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

_, vJdL Ma vw. ndr r e / cprW.Me cIo nev (s. (y :i bn k easdv.nlbg4kt nn i ma m cJ+ n nr h op .one, rce vffC."/N ;

afd m aperd ent .h v v. .. s,-0 4v -] a ddd 2-012384 16.3/4.3-42 3269/0999P:7 i Amend. No. 3,1/84 )

I i

_ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ 8

)

_)

1, .

' INSTRUMENTATION SURVEILLANCE REQUIREMENTS (continued) 5/

p a. At least once perar days by cycling each of the following valves through at least one complete cycle from the running position:

1. (Four) high< pressure turbine stop valves,

2. (Four) high pressure turbine governor valves,

3. (Four) low pressure turbine reheat stop valves,

4. (Four) low pressure turbine reheat intercept valves.

b. .At least once per 31 days by direct observation of the movement

[ of each of the above valves through one complete cycle from the running position.

c. At least once per 18 months by performance of a CHANNEL CALIBRA-

{

TION on the turbine overspeed protection systems.

d. At least once per 40 months by disassembling at least one of ea'ch of the above valves and performing a visual and surface i inspection of valve seats, disks, and stems and verifying no

~

unacceptable flaws or corrosion. 4 i

1-072282 16.3/4.3-64 3218/0624P:7

). )

.h REACTOR COOLANT SYSTEl1 3/4.4.6 REACTOR COOLANT SYSTEli LEAKAGE .,

LEAKAGE DETECTION SYSTEMS LI!11 TING CONDITION FOR OPERATION 3.4.6.1 The followjng Reactor Coolant S.tstem leakage detectier, +,jstens shall be OPERABLE: c ,.

a. The containment atmosphere (gaseous and particulate) r,,,;ac-tivitymonitoringsystemf,and

b. The containment pocket sump level and flow monitorin9 t/s'Am.

3 APPLICABILITY: H0 DES 1, 2, 3, and 4.

^{

ACTION: -

j With tw(e) leakage detection system.sinoperable, be in at least ,- 3 STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the f'/' swing !

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

f

- 1 i

\ l l l l

3-101284 16.3/4.4-20 3272/112'h:- l Amend. P,.1, ;/g4 l Amend. l.... i, 1C/84

) ') .

, [ REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS-

'4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

a. Containment atmosphere (gaseous and/er particulate) monitoring systen6performanc.e of CHANNEL CHECK, CHANNEL CALIBRATI0t{. and CHANNEL FUNCTIONAL TEST at the frequencies specified in t Table 4.3-3A, b

b. Containment pocket sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months, s

3 t

4 3-101284 16.3/4.4-21 3272/1139P!7 l Amend. No. 3, 1/84 i Amend. No. 6, 10/84 )

i h- - - _ _ _ -____m________.-_______.________u_ _ _ _ . _ _ _ _ _ _ _ _

) )

[' '

EMERGENCY CORE COOLING SYSTEMS 3/4.5.5 REFUELIf1G WATER STORAGE TANK LIlllTING CONDITI0ff FOR OPERATION _

3.5.5 - The refueling water storage tank (RWST) shall be OPE d.BLE with: l t

l 1 -

a. A minimum contain,ed borated water volume of 1,180 m di (312,000 gallons),

b. A boron concentration of between 2,000 and 2,100 ppm of ber'm. and c,-- -A winimum-sohtien LeniperatUre of i.6-C U5+Ft:-

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

ACTION:

(

With the refueling' water storage tank inoperable, restore the tank to l OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY / thin 6 hijurs j and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . l SURVEILLANCE REQUIREMEfGS __

4.5.5 The RWST shall be demonstrated OPERABLE:

~

At least once per 7 days by:

a.

1. Verifying the contained borated water volume the ta r,k ,

and

2. Verifying the boron concentration of the water br--At-4 east--once-per-24-hours-by verifying-the-RWST *"+4reto,e _

k when the (outside).-air-temperature-is-Ma Uion 3 M 7 ~

4-101284 16.3/4.5-14 327'; 'll42P : 7 AmV d'

NO 2. 9 @

Ame *

NO- 4. L ld g g f. . d. NO. f, , h' [N*

umamme

CONTAINMENT SYSTEl15 CONTAINMENT LEAKAGE LIl11 TING CONDITION FOR OPERATION !

3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:

1. Less t;,an or equal to La , 0.20 percent by weight of the 3 f 7

containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at Pa, 3.13 kg/cm g g (44.4 psig), or .

I

2. Less than or ennal to 1.. n.10 norenn+ by.:dghtg g

_c_Anttinm air nar 20$oure at4 " educed e o.3ure tof f '

.1,5R yem g (2.2 4_.psig)_. _

b. A combined leakage rate of less than or equal to 0.60 3L for .,

( all penetrations and valves subject to Type B and C tests, when pressurized to Pa* !

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

ACTION: ,

With either ('a) the measured overall integrated containment leakage rate exceeding 0.75 aL or 0.75 Lt, as applicable, or (b) with the measured combined leakage rate for all penetrations.and valves subject to Types B and C tests exceeding 0.60 L,, restore the overall integrated leakage rate to less than or equal to 0.75 L, or less than or equal to 0.75 Lg, j as applicable, and the combined leakage rate for all penetrations subject to Type B and C tests to'less than or equal to 0.60 L, prior to increas-ing the Reactor Coolant System temperature above 200"F.

o i

l 4-101284 16.3/4.6A-3 3272/1126P:7 !

Amend. No. 2, 9/83 !

Amend. No. 3, 1/84 Amend. No. 6,10/B4 l

m

_ ')[ f c ,

a-. CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (continued)

b. At least once per 6 months by:

1. Verifying the contained solution volume in the tank, and p.

2. Verifying the concentration of the NaOH solution by chemical analysis.

,e L c._ At least o'nce per 18 months during shutdown, by verifying that each automatic valve in the flow path actuates to its correct-position on a containment spray test signal.

.~

d. At least once per 5 years by verifying eductor suction flow rate (to be-determined during pre-operational tests) from the RWST:

N. "

1. Eductor No. 1 -+ 1 m3/hr.(4 gpm) 4

2. Eductor No. 2 + 1 m3 /hr (4 gpm) with containment spray pump in recirculation.(via test line) and the spray additive tank d'ischarge isolation valve closed.'

, d MttefEs' AT LEAST ONCE PER S YE ARS _ HEM 0NSTRATE THAT A l FLOW PATH EXISTS. FHOM Till* SPliAY ADDITIVC T ANir VI A THE - !

+ ALOLATION VALVES 10 A LOCAL GANPLE C0llNLCTION DY VERIFY 1NG !

A FLOW RATE OF AT LEAST //////CPH ./TO DE DETERMINED DURING PRE-OPEkAT10llAL TESTS /. jun-s0ity . l 7 H0TC/ REFERRING To FSAll FIGURE 6.2-44 FLOW PATH ,

CHALL BE FRON SPRAY' ADDITIVE TANK THROUGH i PIP 1HG 2-SI-151Ri THROUGH VALVES 9050A AND i P THROUGH TE-809 THROUGH DRAllCH LINE i 3/4-51-151R AND VALVE 9070s CONCLUD!llG AT TEST C 0 Nile C T10tl. VALVES 9072 9073i 9071A AND D e 90t1 A AllD D EkALL DE CLGEED 0VRING TillL TELT 10 Mill! Nile EX1EllT OF FL0W PATif.

\

2-041584 16.3/4.6A-19 3270/1050P:7 Amend. No. 4, 4/84 l>

9

_11_______2_____._______________

)

W

. } 1

.(. / l DEFINITIONS :

7 k

1 PRESSURE B0UNDARY LEAKAGE

1 1

1.21 i PRESSURE BOUNDARY LEAKAGE shall be leakage (except lf !.

tube leakage) through a nonisolable fault in a Reactor Coblent Sys component body, pipe wall, or vessel wall. l QUADRANT POWER TILT RATIG 1.22 QUADRANT POWER TILT RATIO shall be the ratio of the Inoxim \1 4 excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum IWer excore detector calibrated output to the average of the lower excore detector '

caliLrated outputs, whichever is greater.

With one excore detector I inoperable, the remaining three detectors shall be used for average. computing.the -

RATED THERML POWER 1.23 RATED THERMAL POWER shall be a total reactor corerate transfer hea l2 to the reactor coolant of 1,876 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME '

i 1.24 The REACTOR TRIP SYSTEM RESPONSE TIME shall be t beginning 'when the monitored parat.*eter exceeds its trip setpeint . 2 j channel sensor and ending with loss of stationary gripper ceP vcitage REPORTABLE OGCUPPE C b E VE// T SVGtW~

1.25 A REPORTABLE OC@RRENCE shall be any of those conditionw sp in Specif foat tons 6.9. l'0 and C.?.1.9.

2 i

t

.Sc.cten A.M to /0 CM- Auct.60 a^ci Statere#s " thee -n 4 -al

)?AFC .*gafaftoa ch yrma -z 2-093083

} 16.1-7 3268 '0 7 Ames ,925iS:

be . 2, 9/83 w__ __ _ _ _ _ _ _ - - -

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c. .

s t

l

. DEFINITIONS Sm ii ketiens referring-to 'PAEC" cT tittr-*CormHs4or." bth refer-tc the--

E PM14 wine Atweic Enertjy Conmb:f or..-

SHIELD BUILDING INTEGRITY 1.26 SHIELD BUILDING-INTEGRITY shall exist when: 'l2 I

a. Each door in each access opening is closed except when the- I access opening is being used for normal transit entry and exit, I then-at least one door-shall be closed.

b. The shield building filtration system is OPERABLE.

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

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

SHUTDOWN MARGIN 1.27 The SHUTDOWN MARGIN shall be: 2 1

a. The amount of reactivity by which the reactor is suberitical, or

b. The amount of reactivity by which the reactor shall become sub-critical as a result' of the open,ing of the reactor. trip breakers, assuming the reactivity associated with the single rod 2

cluster assembly of highest worth is unavailable for insertion.

SLAVE RELAY TEST i

1.28 A SLAVE RELAY TEST shall be the energization of each slave relay and lf. ' l I

verification of OPERABILITY of each relay.

The SLAVE RELAY TEST shall t

r T(. ,

l 2-093083 16.1-8 3268/0926P:7 Amend. No. 2, 9/83 V

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-( i ADMINISTRATIVE CONTROLS ._ q

. (I. i a

UNIT STAFF (continued) >

c. A Health Physicist shall be onsite when fuel is in the reacte,r.-

d. ALL CORE ALTERATIONS shall be observed and directly supervited by either a licensed Senior Reactor Operator or Senior Rectt.<>r Operator Limited to Fuel Handling who has no other concurrbot.

responsibilities during this operation.

I

e. A site Fire Brigade of at least 5 members shall be maintained onsite at all times.* The Fire Brigade shall not include 3 men. 1 bers of the minimum shift crew necessary for safe shutdown oi the unit and any personnel required for other essential functions during a fire emergency.

6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)_

[

1 (This portion of the Plant Technical Specifications will be added 1tter.)

60t

.Gx /,v on" l'l /MC7 a ./ !

I i

1 i

for />

The Fire Brigade composition may be less than the minimum requirer <.r.t a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to ac f

16.6-2 3272/lll8F:7 ,

3-101284 Amend. No. 2, g/83 Amend. No. (,, ;0/84 i

~

(

( ,

ADMINISTRATIVE CONTROLS j 6.2.3 ' INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) {

FUNCTION l

1-6.2.3.1.The ISEG shall function to examine plant operatirig chi *!cteristics, !

! HRC-issuances, industry advisories, Licensee Event Reports and v.ner sources I of plant design and operating experience inf ormation, includit,5 olants of similar. design, which may indicate areas for improving plant 54 p.y, l i'

i COMPOSITION i

6.2.3.2 The ISEG shall be composed of at least five, dedicate < full-time engineers located on site. <

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveil inte of plant activities to provide independent veri,fication* that these act' .ities are j performed correctly and that human errors are reduced as much m practical.

AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations fcr revWd procedures /

equipment modifications, maintenance activities, operations ac'ivities or other means of improving plant safety to (a high level corporW official in.a.t qchnically oriented position who is not in the et .agemen. chain for power" production).

6.2.4 SHIFT TECHNICAL ADVISOR ,

The Shif t Technical Advisor shall provide technical se Ocrt tt the Shif t Super-visor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.

6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each mec.ber of the unit staff shall meet or ex:ted tht minimum qualifi- ;

)

cations of (ANSI N18.1-1971). -

Minimum qualifications for members of the unit staff 11all to specified by use of an overall qualification state' ment ref erencing (ar. mS15.mdard agreed to by the NRC staff) or alternately by specifyir.g individut' :ositbn qualifications.

'. Generally, the first method is preferable; however, t e secor< method is adaptable to those unit staffs requiring special qual"icatio, statements l

{ because' of a unique organizr.tional struciare, j 0

"Not responsible for sign-off function.

ALL STS 6-7

. g -. . _ ,

.m

(. k. .

TABLE 6.2-1 (continued) )

b

p,c ,ph,1 _@ ff iA2p u:ga' w afG' > 4..?i / s.tii&, - It;?. D,:a s Ar'th-

.,,.tiai anzae. -a co, Quwdu<g Cy< <,re. <, aeg g q s , + , n i. f J y' -

p* Licensed-+pera re cha11 nat vor.k.r4ra. 9 m -

Na,dfro.<<,:a diae>:ol*fs4d w f ii< # pr.ci.e //e, . ,, ,

1. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months straight,

2. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period,

3. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, ori<:

4. 14 consecutive days without havir.*a 2 consecutive 'tys of f.

. l i

i

-t

Deviation from these requirements tu.j t,e authorized ' the (Plant Manager) in accordance with estabitued procedures p .d with docu- i mentation of the cause. Overtime ' Nits do not incide Ehift turnover time.

.x x/Qf A % 5% n A uce:rsL .

4 as..c ,,,,n ?,.,4 64 .. ' u..,y,,w/.(, y ,t9 ,

ewd p f waiw f mau /i. .' u, qipi+, ,c4'.< 7

& ce.4M'A 'i L. / . ord es!d 4<& Wm p.9 cscp$ cf. ia/cGJ n, .c&

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- :p c.'? m, ,

E '.- 5 3T/P/ll20P:7 3-101284- /*und. No. 2, 9/83 laund. No. 6,10/84

l

( (

ADM1HISTRATIVE CONTROLS RESPONSIBILITIES (continued) ,,

a. Review of: (1) all procedures requireo by Technical Specif t-cation 6.8 and changes thereto; (2) all programs required by Technical Specifications 6.8 and changes thereto; and (3) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety.

b. Review of all proposed tests and experiments that affect nucler.r safety.

c. Review of all proposed changes to Appendix A Tech'nical l

Specifications.

l' d. Review of all proposed changes or modifications to unit syst6w.

or equipment that affect nuclear safety,

e. Investigation of all violations of the Technical Specificatiore, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Plant Manager and to the Safety Review Committee (SRC).

g p2 K a r.s &.s s v5 hrs.

f. Review of %re;nivinn 74-hnur written nntific144on to tW Pb"ippirie Atomic-Energy rnarniginn t o q4+.

1 9

Review of unit operations to detect potential nuclear safety hazards,

h. Performance of special. reviews, investigations or analyses and 2 reports thereon as requested by the Plant Manager or the Safety Review Committee. ,

(, .

2-093083 10.6-8 3268/0906P:7 Amend. No. 2, 9/63

- 4 ADli1HISTRATIVE CONTROLS '

( -

j-REVIEW >

l 6.5.2.7 The SRC shall review: ;

(1) changes to procedures, equip-

a. The safety evaluations for :

ment, or systems, and (2) tests or experiments completed l unde' 4 /;/,

the provision of 10 CFR, Section 50.59, (Partnot 7, Code of PA l Regulations, Section 51) to verify that such actions diti constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment, or systems whi involve an unreviewed safety question as defined in 10 CFR, , 4 Section 50.59 (Part 7, Code of PAEC Regulations, Sectiren 51 j

c. Proposed tests or experiments which involve an -ur, revie question as defined in 10 CFR, Section 50.59 (Part 7, C

,' PAEC Regulations, Section 51). -

d. Proposed changes to Technical Specifications or this Ope License.

j Violations of codes, regulations, orders, Technical Specifica-

e. ]

tions, license requirements, or internal piecedures or instructions having nuclear safety significance.

f.

Significant operating abnormalities or deviatic's from n and expected performance of unit equipment that affect safety.

gz( ne n>crA & E e w n %requi %; ?4-%0r--w4tten netificat4 g . j ree+:

3270/1009P:7 i .

16.6-12 Ame nd . N o . L . , ,8',

2-041584 1

W

7 4;:' - ,

( (

t l

.4'

- ADMINISTRATIVE CONTROLS "

t.

REVIEW (continued) >

h. All recognized indications of an unanticipated deficiency in-some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

H

i. Reports and meeting minutes of PORC.

AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the SRC. These audits shall encompass:

a. The conformance of unit operations to provisions conta'ined within the Technical Specifications and applicable license. .

conditions at least once per 12 months.

{

b. The performance, training, and qualifications of the entire unit staff at least once per 12 months. ;

c. The results of actions taken to correct deficiencies occurring j.

in unit equipment, structures, systems, or methods of operation that affect nuclear safety at least once per 6 months.

I

d. The performance of activities required by the Operational Qual-ity Assurance Program to meet the criteria of 10 CFR, Part 50, Appendix B, (Part 7, Code of PAEC Regulations, Appendix B), at (4 .l least once per 24 months. ,

e. The Emergency Plan and' implementing procedures at least once per

/t JW months. .

2-041584 16.6-13 3270/1009P:7 Amend. No. 4, 4/84 1

( (

p- I' ADMINISTRATIVE CONTROLS AUDITS.(continued) f.

The Security Plan and implementing procedures at least ohl e per

/2. E months.

g.

Any other area of unit operation considered appropriate IW the SRC or the Vice'-President responsible for Nuclear Power.

2 l!

h. The Fire Protection Program and implementing procedures al- least once per 24 months.

l i.

An independent fire protection and loss prevention inspect. ion and audit shall be performed annually utilizing either quhlified I offsite licensee personnel or an outside fire protection firm. !

I j.

An inspection and audit of the fire protection and loss p e_ !

vention program shall be performed by an outside qualifieil' fire consultant at intervals no greater than 3 years,

k. The radiological environmental monitoring program and the results thereof at least once per 12 months.

1. The OFFSITE DOSE CALCULATION MANUAL and implementing procbdures at least once per 24 months.

m. The PROCESS CONTROL PROGRAM and implementing procedures foi. 3 solidification of radioactive wastes at least once per 24 tuonths.

n. The performance of activities required by the Quality Assurance ProCram to meet the criteria of the latest revision of Retiula-tory Guide 4.15, at least once per 12 months.

( '

I 3-012384 16.6-14 3269/0987Pt7 Amend. No, t, 9/83 Amend. No. 3, 1/84 I

( ( 'd.

J,.. !

ADMINISTRATIVE CONTROLS RECORDS (continued) /fc and ,. ci forHordCN N V ' N ' '*I'I' '

a. Minutes of each SRC meeting shall be preparbn d and mtSc. approved Jew Nw/m>' Aw

4 g within 14 days following each meeting.

i

b. Reports of reviews encompassed by 6.5.2.7 above, shall be' prepared and approved,within 14 days following completion,of the 2.

review, 0' &'" N

0 "i0'"Y

]5,yonci

,- c. fb.fe.'I"N N N" t , a , ,.

i Jac/ec>s

c. Audit reports encompassed by 6.5.2.8 above, shall be forwarded' to the management positions responsible for the areas audited within 0 s after completion of the audit ty the auditing 2. !

organization. De ICV d'n l /~rSf'" it O & i

( Nuchcv fe-:. i w an,/ J6 H,e ..

l. 6.6 REPORTABLE O N E ACTION evs45.

6.6.1 The following actions shall be taken for REPORTABLE GCCURRENC4Hi:

a. The PAEC shall be notified and/or a report submitted pursuant to the requirements of Specifict' = C.O. WME 76/0 /ON6D ad cD 9M2VEMr~ PBC "pM/S - j

b. Each REPORTABLE OCC"RRO:L requir %g 2Mour-- notificat4e-to-the-P-AEC shall be reviewe.d by PORC and submitted to the SRC, er.4-the

~

P1:nt".: nager.

6.7 SAFETY LIMIT VIOLATION 1 l

1 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

I i

2-093083 16.6-15 3260/0906P:7 Amend. No. 2, 9/83

.! t

( -(

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (continued) >

a. The unit shall be placec' in at least HOT STANDBY within one. hour.

i

b. The PAEC Operations Center shall be notified by telephone as. ,

soon as possible and in all cases within one hour. The SRC g

shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by PORC. This report shall describe:

(1) applicable circumstances preceding the violation; (2') effects of the violation upon facility components, systems j or structures; and (3) corrective action taken to prevent ;

recurrence.

d. The Safety Limit Violation Report shall be submitted to the PAEC, the SRC and the Plant Manager within 14 days of the violation. . .

e. Cntical epwM Oj @e ud T sW NW b W mThorjted $ OE PW '

6.8 PROCEDURES AND PROGRAMS 6.8.1- Written procedures shall be established, implemented, and main-l tained covering the activities referenced below:

l

a. The applicable procedures recommended in Regulatory Guide 1.33, Appendix A Revision 2, February 1978. l

b. Refueling operations. *

c. Surveillance and test activities of safety-related equipment.

/

.k ,

2-093083 . 16.6-10 3268/0906P:7 Amend. No. 2, 9/63

. 'M

k (. [fM 'i ADMINISTRATIVE CONTROLS {

i !

1 PROCEDURES (continued) 1 '

Identification of the procedures used to measure the values (ii) of the critical variables; 1 Identification of process sampling points; (iii)

(iv) Procedures for the recording and management of data; f

Procedures defining corrective actions for all tontrol (v) point chemistry conditions; (a) the authority responsible for (vi) A procedure identifying:

the interpretation of the data, and (b) the sequence and f timing of administrative events required to initiate '

corrective action; and c k

Monitoring of the condensate at the discharge of the con-(vii) When l densate pumps for evidence of condenser in leakage.

hall be condenser in leakage is confirmed, the leai repaired, plugged, or isolated within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . !

.6ee. ln.cs4 -+

6.9 REPORTING RE0VIREMENTS ROUTINE REPORT 5 MartCP"I'. CCCUPE".CE_S -

~.

1 6.9.1 In addition to the applicable reporting requirements of 10 CFR, th following reports shall be submitted to PAEC unless otherwise noted i

/

\

3218/0640P:7 16.6-19 l-072282

-N

,,~,-,--

(

d.. Backup'Mothod for Determining Subcooling. Margin

(PWRs with a single channel of monitoring / ins--

trumentation)

A' program which will ensure the capability to accurately monitor the Reacto,r Coolant system subcooling margin.

The program shall include the following:

.i. Training of personnel, and

11. Procedures for monitoring

e. Postaccident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulate in plant gaseous effluents, and contajn-j mentLatmosphere samples under accident conditions. '

The program shall include the following:'

1. Training of personnel ii.' Procedures for sampling and analysis iii. Provisions for maintenance of sampling and anlysis equipment.

4 1

1 S .

l l

. l l

l

. _ _ - - _ _ _ h

( W l w

{ ADMINISTRATIVE C0llTROLS M0tiTHLY OPERATItiG REPORT i

6 .9 .1.6 Routine reports of operating. statistics and shutdown experience, l including documentation of all changes to power-operated relief valves (PORV's) or safety valves, shall be submitted on a monthly basis to PAEC l no later than the 15th of,each month following the calendar month covered ,

by the report.

Any changes to the OFFSITE DOSE CALCULATI0fi MAliUAL shall be submitted with I the Monthly Operating Report within 90 days in which the change (s) was j made effective. in addition, a report of any major changes to the radio- 3 l active waste treatment systems shall be submitted with the Monthly Operat- l ing Report for the period in which the evaluation was reviewed and accepted by the Plant Operation Review Committee (PORC). j

.: J ~\

( 6.YN7 The n:PORTI,0LE CCCLIRREiiCE3 -of Specifications 6 ' W EId 6.9.1.9 below, inclu ' corrective actions and meae o prevent recurrence, shall be reported to FM sup al reports may be required to fully-J3 b describe final resolu of occ . In case of corrected or t.upple-mental repor , a licensee event repcrt shal weapleted and reference shall e made to the original report date.

F4GECTIFICATiGH'ITH WRITTEli FCLL4WlP-- .odz.eq 6.9.1. he types of events listed beloi shall be reporte n 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by t hone and confirmed by tele ph(rIrlgram, or fatt.imile transmission to P AE'C later than the f-i working day following the event, with a written followu ort within 14 days. The written followup report shall in 1 a.s a mini, completed copy of a licensee event report form. Information provided errec nsee event repor psbl be supplemented, as needed, by additional n'arcative

(

2-012384 16.6-22 3269/0980l':7 Amend. No. 3.1/84 i

).

( l i

[

3.

ADMINISTRATIVE CONTROLS RADI AL PEAKING FACTOR LIMIT REPORT ,,

6. 9 /. F \

6..l.10 The F xy limit for Rated Thermal power (FR P) shall be pr.o-vided to the PAEC for all core planes containing bank "D" control rods and.

all unrodded core planes at least 60 days prior to cycle initial critical-ity. In the event that t,he limit would be submitted at some other time.

during core life,. it will be submitted 60 days prior to the date the limit would become effective unless otherwise' exempted by the PAEC.

Any information needed to support F{P will be by request from the PAEC and need not be included in this report. '

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2-012384 16.6-27 3269/0988P:7 Amend. No. 3, 1/84

p- ,

I ADMINISTRATIVE CONTROLS f

RECORDRETENTION(continued) 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval'at .

each power level,

b. Records and logs of principal maintenance activities, inspec-tions, repair, and replacement of principal items of equipment related to nuclear safety, pvewT6.

c. ALL REPORTABLE O h -w w5 submitted to PAEC.

d. Records of' surveillance activities, inspections, and calibra-tions required by these Technical Specifications. ,., .

(

e. Records of changes made to the procedures required by Specification 6.8.1.

f. Records of radioactive shipments.

.g. Records of sealed source and fission detector leak tests and results.

h. Records of annual ph'ysical inveatory of all sealed source a

material of record.

6.10.2 The following records shall be retained for the duration of the Unit Operating License:

1-072282 16.6-29 3218/0640P:7

- __-____________-___n

,W

,/ ADMINISTRATIVE CONTROLS C :::AL "7 1 T.I.S M

.9.2 Special reports shall be submitted to the PAEC within he time-p riod specified for each report. These reports shall b ubmitted {

cov ring the activities identified below pursuant to e requirements of i the a licable reference specification: )

a. ECCS actuation, Specifications 3.5. /and 3.5.3. l

b. In perable seismic monitoring ' instrumentation, Spec fication 3.3.3.3. .

c. Incperabl ,meteorologif 1 monitoring instruInentation, Specificatid 3.3.3. . . ,.

-f d. Seismic event aryi ysis, Specification 4.3.3.3.2.

e. Inoperable ire detec instrumentation, Specification 3.3.3.8.

f.

Inoperpefiresuppressio) system, Specifications 3.7.11.1to 3.7.1 .6.

g. operable fire barrier penetratio Specification 3.7.12.

h. Inoperable temperature monitoring, Spe fication 3.7.13.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of 10 CFR, the following records shall be retained for at least the minimum period indicated. l

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, l l 2-101284 16.6-28 3272/ll19P:7 )

l Amend. No. 6, 10/84 I

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( i PLANT SYSTEMS j 3/4.7.5 -ULTIMATE HEAT SINK lt LIMITING CONDITION FOR OPERATION 3.7.5 The ultimate heat sink shall be OPERABLE with:

a.

m ~ .. ...... ,

A minimum water level =+ - d:;: :?r;;tur 17.005 : ",;r 0;;

2

b. An asient air temperature f,31.1*C w.b. (88'F) and 31.1'C d.b. l2

c. Two independent cooling towers shall be operable, with two fans per cooling tower. 2 APPLICABILITY: MODES 1, 2, 3, and 4. -

ACTION:

With the requirements of items a and b of the above specification not h satisfied, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . -

With only one cooling tower operable, restore second coolfng tower to operable 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 within 6 I he: Ts and in COLD $!iUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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2-093083 16.3/4.7-15 3268/0947P:7 Amend. No. 2, 9/83

f 9

PLANT SYSTEMS 3/4.7.6 CONTROL ROOH VENTILATION SYSTEft d LIMITING CONDITION FOR OPERATION i

3.7.6 Two redundant control room charcoal cleanup systems fans and b '

plenums shall be OPERABLE and two redundant main control room air con-ditioning systems shall be operable.

APPLICABILITY: ALL MODES.

ACTION:

MODES 1, 2, 3, and 4:

&N as:n amlrose a.te undinomin3 s@m)

Withonemaincontrolroomcharcoalcleanupsystem/'r=;'r-"-inoper-

. cble, restore the inoperable system to OPERABLE status within 7 days or be

( in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . j

,. MODES 5 and 6:

a. With one main control room charcoal cleanup system fan or plenum inoperable, restore the inoperable system to OPE.RABLE status within 7 days or initiate and maintain operation of the remain-ing OPERABLE control room emergency air cleanup system in the i recirculation mode.

l

b. With both main control room charcoal cieanup systems inoperable, or with the OPERABLE main control room charcoal cleanup system required to'be in the recirculation mode by ACTION (a) and not capable of being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

2-101284 16.3/4.7-16 3272/ll43P:7 Amend. No. 6, 10/84

\ \

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.6 Each main control room ,:x charcoal x shall& nd ms; n con cleanup system { _

trol rw sie ca.a

, h ,%

he demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is'1ess than or equal to 26.7'C (80*F).

b. At least once pt'r 31 days on a STAGGERED TEST BASIS by initiat-ing, from the co1 trol room, flow through the HEPA filters,and charcoal adsorbers and verifying that the system operates for at .i least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

c. At least once per 18 months or: (1) after any structural main- l tenance on the HEPA filter or charcoal adsorber housings; or (2) following painting, fire, or chemical release in any venti-lation zone connunicating with the system by:

1. Verifying that with the system operating at a flow rate of 28,350 cfm i 10 percent and exhausting through the HEPA ,

filters and charcoal adsorbers, the total bypass flow of the system to the facility vent, including leakage through the system-diverting valves, is less than or equal to 1 percent when the system is tested by admitting ccid DOP at the system intake. (Forsystemswithdivertingvalves.)

2. Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a. C.5.c. and C.5.d of Regulatory Guide 1.52, Revision 1 July 1976, and the system flow rate is 28,350 cfm i 10 percent.

2-101284 16.3/4.7-17 3272/1143P:7 Amend. No. 6,10/84

h c

PLANT SYSTEMS CO2 SYSTEMS l

LIMITING CONDITION FOR OPERATION

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3.7.9.3 The following high pressure ...

(

J ::= CO systems shall l 2

be OFERABLE:

I

a. High pressure Train A Battery and Battery Charger Rooms system, '

l Intermediate Buildivg, elevation 100.3 m. I 1 i

b. High pressure Train B Battery and Battery Charger Rooms system, ;

Intermediate Building, elevation 100.3 m.

APPLICABILITY: Whenever equipment protected by the CO systems is 2

required to be OPERABLE, I ACTION:

i

s. With one or more of the above required C02 systems inoperable, within one hour estabitsh a continuous fire watch with backup i

fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, estab-lish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, in lieu of any other rsport required by specification 6.9.1, prepare and submit a special Report to the Coenission pursuant to specification 6.9.2 within the next ;

30' days outlining the action taken, the cause of the inoperabil-ity, and the plans and schedule for restoring the system to l CPERABLE status.

3-101284 16.3/4.7-41 3272/1144P:7 Amend. No. 2, 9/83 Amend. No. 6, 10/84

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[ 'd UNITED STATES

- '3' f, NUCLEAR REGULATORY COMMISSION j

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2 WASHINGTON, D. C. 20066

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~$s,,,,

e.

FROM: J. D. LAFLEUR ORIO. DUE DATE: T11f07F83- TICKET NO: 2 9361 '

DOC DATE: 10/28/83 TO: H. R. DENTON NRR RCVD DATE: 10/31/83

- YELLOW **

FOR SIONATURE OF H. DENTON sj l

DESC: CC: l PHILIPPINE FSAR' REVIEW TEAM MISSION-- DENTON/ CASE 1 FUNCHES

1. VOLLMER REFERRED TO: DL DATE: 10/31/83 2. MATTSON !

CONTACT: % 3. THOMPSON

4. SPEIS l

gg 5. ORACE i

[ h 66 assef a8j k '

6. SNYDER

%.7.' essy 64d *

5. A 3 j CO n/

PLEASE REVIEW THE DUE DATE IMMEDIATELY:.

I IF THE DUE DATE DOES NOT ALLOW ADEQUATE REQUESTS FOR REVISION OF YELLOW TIME TO RESPOND TO THIS TICKET, YOU MAY TICKET DUE DATES MAY BE MADE, WITH I f JUSTIFICATION, THRU THE WEEKLY WITS REQUEST A REVISED DUE DATE. THE REQUEST ,

MUST INCLUDE A VALID JUSTIFICATION AND UPDATE UP TO ONE WEEK AFTER ASSIGN-BE MADE THROUGH YOUR CORRESPONDENCE CO- MENT BY NRR MAIL ROOM. THE NEW CUE ORDINATOR TO THE NRR MAIL ROOM (KAREN DATE, IF APPROVED BY NRR MAILROOM, BOWMAN OR MELANIE GARVER). WILL BE USED TO TRACK DIVISION'COR-DESPONDENCE COMPLETION SCHEDULES.

i PLEASE DO NOT HAND CARRY CONCURRENCE PACKAGES TO DIRECTORS OFFICE WITHOUT FIRST OOING THRU THE NRR MAIL ROOM.

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l 4- R.:Vt'02IM/1.00021 Lirie 1 l .,

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-VIA WUI l .NRC-BHD WSH &Jgo 66804 PAEC PN .

.66804 PAEC PN

~TOI B..I.YOUNGBLOOD CHIEF. LICENSINO UNANCH I USNRSC

'OUR. TELEX OF 16 NOVEMBER INADVERTENTLY OMITTED CHAPTERS 11 AND ,

12. PLEASE INCLUDE THE FOLLOWING 11.1 SOURCE TERMS 11.2 LIQUID WASTE SYSTEMS l

11.5 GASEOUS WASTE PROCESSING SYSTEM 11.4 PROCESS AND EFFLUENT RADIATION MONITORING SYSTEM

-11.5 SOLID WASTE SYSTEMS ~

11.6 OFFSITE RADIOLOGICAL MONITORING PROGRAM 3 l 12.1. SHIELDING 12.2. VENTILATION

-12.3 HEALTH PHYSICS PROGRAM BARTOLOME PHILATOMIC NRC-BHD WSH .

t NRC-BHD'WSH }

NRC-BHD WSH NRC-BHD WSH ;

Timwi OS: 46 12/05/83 EST Connect Time 118 seconds i

I 6

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--_ - - - - _ _

ML20244B557

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