ML18095A246

Proposed Tech Specs Re Organizational Changes & Revised Reporting Requirements

ML18095A246
Person / Time
Site:	Salem
Issue date:	05/31/1990
From:	Public Service Enterprise Group
To:
Shared Package
ML18095A245	List: ML18095A244 ML18095A246
References
NUDOCS 9006060082
Download: ML18095A246 (135)

Text

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UNIT l MARKUP PAGES

DEF!N!TIONS SECIION 1.0 Q!iE1N1TlQNS DEFINED TERMS ACTION AXIAL FLUX DIFFERENCE CHANNEL CALIBRATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CONTAINMENT INTEGRITY CONTR.OLLED LEAKAGE

• coRE ALTERATION DOSE EQUIVALENT I*l3l E*AVERAGE DISINTEGRATION ENERGY ENGINEERED SAFETY FEATURE RESPONSE TIME FREQUENCY NOTATION FULLY WITHDRAWN GASEOUS RADWASTE TREATMENT SYSTEM IDENTIFIED LEAlCAGE MEKBEl.(S) OF THE PUBLIC OFFSITE DOSE CALCUIATION MANUAL (ODCM)

OPERABLE

• OPERABILITY OPERATIONAL MODE PHYSICS TESTS PRESSUll.E BOUNDARY LEAKAGE PROCESS CONTROL PROGRAM (PCP)

PURGE* PURGING QUADRANT POVE!l TILT RATIO RATED THERMAL POWER.

REACTOR TRIP.SYSTEM RESPONSE TIME REPORTABLE "'oGGUll:HN6E SHUTDOWN MARGIN SITE BOUNDARY SOLIDIFICATION SOURCE CHECK STAGGERED TEST BASIS THERMAL POWER.

UNIDENTIFIED LEIJCAGE UNRESTRICTED A1lEA VENTIIATION EXHAUST TREATMENT SYSTEM VENTING SALEM

• UNIT l

- I l*l l-l 1-l 1-1 1-1 1-1 1-2 l-2 l-2 1-2 l-3 1-3 l-3 1-3 l-3 l-3 1-4 1-4 l-4 l-4 1*5 l-5 1-5 l-5 l-5 1-5 1-6 1-6 1-6 l-6 l-6 l-6 1-6 l-7 l-7 1-7 1°7 1-7 All*~daanc No. 101

. j

ADMINISTRATIVE CONTROLS

=============================================================

SECTION 6.1 RESPONSIBILITY

- =

6.2 ORGANIZATION J

Onsite and Offsite Orqanizations Facility Staff.......

Shift Technical Advisor 6.3 FACILITY STAFF QUALIFICATION 6.4 TRAINING....

6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE Function.

Coaposition...

Alternates Meeting Frequency Quorua.....

I SoRC I Responsibilities

) Review Process...

Authority....

Record<l-I s crncf /Geporfs j 6.5.2 NUCLEAR SAFETY REVIEW*(

j llflJD AUDIT I Function.......

Composition......

Consultants......

ls-~Fefy I Of f<;$SitetReview 6-r-eup

• eview

---

~Audits * * *........

On~ite Safety Review Group Reapauai_bilities Authority..

SALEM - UNIT 1 XVIII PAGE 6-l 6-1 6-1 6-17 6-S7 6-17 6-if 8 6-J/ 9 6-lf 'i 6-i 9 6-;f 'd 6-$9 6-1/0 6-f/O 6-f /0 6-9' '"

6-S I()

6-~,,

6-9<<1/

6-1-0 l:J 6 - ],6'" I':~.

6-J;r 13 6-111'/

6-'J..l" I'/

c-11 Amendment No.99

ADMINISTRATIVE CONTROLS

=============================================================

SECTION 6.5.3 TECHNICAL REVIEY AND CONTROL 6.6 REPORTABLE EVENT ACTION 6.7 SAFETY LIMIT VIOLATION 6.8 PROCEDURES AND PROGRAMS 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS 6.9.2 SPECIAL REPORTS 6.10 RECORD RETENTION...

6.11 RADIATION PROTECTION PROGRAM 6.12 HIGH RADIATION AREA...

6.13 PROCESS CONTROL P.ROGRAM.

6.14 OFFSITE DOSE CALCULATION MANUAL 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS

• 6.16 ENVIRONMENTAL QUALIFICATION SALEM - UNIT 1 XIX

• 6-~ IS 6-'NJ:l 15 6-NP /b 6-"'N-

/b 6->> 19 6-)3: J3 6-X'~3

. 6-~ ;)5°

. 6-.k!oi.5 Amendment No. gg I -

~ec fio'J b"o. 7 3 To I ocFR fQ.1t !)O.

DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE OCCl:JRR:F.NC!

1.27 A REPORTABLE OCCUR:R!:NC! shall be any of those conditions specified in Speeifieatieas 6a9ala8 and §.9.1.9.

SHUTDOWN MARGIN 1.28-SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be FULLY WITHDRAWN.

SITE BOUNDARY 1.29 The SIT! BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3, and which defines the exclusion area as shown in Figure 5.1-1.

SOLIDIFICATION 1.30 SOLIDIFICATION shall be the conversion of wet radioactive wastes into a form that meets shipping and burial ground requirements.

SOURCE CHECK 1.31 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of:

(n)

a.

A test schedule for~ystems, subsystems, trains, or other dasignatK.*ccmponents"obtained.- by'* dividing* the specified"* tes1t

• interval*. intcx A'. equal. subintervals:,*.*.

inf SALEM - UNIT l 1-6.:-

Amendment No. 91

!NSTRUMENTAT!ON RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONOITIO.l_FOR OPERATION 3.3.3.S The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alann/trip setpoints set to ensure that the limits of Specification 3.11.l.l are not exceeded.

The alann/trip setpoints of these channels shall be determined in accordance with the OFFSITE COSE CALCULATION MANUAL (OOCM).

APPLICABILITY:

At all times.

ACTION:

a.

With a radioactive liqui-d effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or decla~a the channel inoperable or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumef'.ltation channels OPERABLE, take the ACTION shown in Table 3.3-12. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next semi-annual radioactive effluent release report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3~.o.4(/l!!iill 6.9.l.9.~ are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.S Each radioactive liquid *effluent monitoring instrumentation channel sha l 1 be demonstrated OPERABLE by performance of the CHANNEL CHEC:<,

• SOURCE CHEC:<, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.

SALEM - UNIT l 3/4 3-58 Amendment No. 59

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDlTION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent rronitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.2.l are not exceeded.

The alarm/trip setpoints of these channels shall be determined in accordance with the (OoocM(.

APPLICABILITY:

As shown in TablP. 3.3-13 ACTION:

a.

With a radioactive gaseous effluent monitoring

• instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive gaseous effluents monitcred by.the affected channel or declare.

the channel inoperable or change the setpoint so it is acceptably conservative.

b.

With less than the mini111Jm number of radioactive gaseous effluent monitoring instrunentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next semi-annual radioactive effluent release report why the inoperability was no~ *corrected in a timely manner.

c. The provisions of Specifications 3.0.3J'..C:3.0.4/@nd/

6.9.l.9.b are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, ANO CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

SALEM - UN IT l 3/4 3-64 Amendm.ent No. 79

REACTOR COOLANT SYSi:M StJRVEILL~NCE REOU!REMENTS (Continu~)

-~.

c.

Results of steam generator tube inspections '-"h1ch fali into Catlgal'""/ C-3 IAG ~1qwirt ~~~?; A;;ific1tiaA ef ti!: CelMlissieA snal1 ~* "4~;rilG P~FIW*At ;s Sp1eifi;&t1a~ s.;.1 ~FiQF;;

F'H~tiQA Qf phR~ Cl~IP'UieR. Th* WJPiUeA felTS\\-WS ef ':.ll'fc 1"119er*.~shal l provide a description of 1nvest1gations conc:ucte~

to d1tl rnrf n1 caus1 of the tube cegrada t1 on and eorrtc-:ive rr.e!sur!s taken :a prevent recu~nce.

S~4// IJe e~/1<~fJ -fi:,; iefbr-kh,*/;-1-y fuf"_sttru(f -lb toe F'R. S-o. 7 'J.. a.nol. 1oc;:te.Oe>. 7 3., T/.e e v'et/L<.~ f-io11 s hcd J J,,e, doc.Gt /17 t!?,n f PJ. C.. /) o{_

SAU?~ - UiHi I j/ :! !-1 !

TABLE 4.4-2 STEAM OENEllATOR TUDE INSPECTION ISi SAMPLE INSPECTION 2NO SAMPLE INSPECTION 3RD SAMPLt: INSPECTION Saanplo s1..

ll11ull

• Action Required Hinill

• Acllon Required Result

• Action ltcqulred I

A mlnlmumol C-1 None N/A N/A NII\\

N/A S T1il111 pu

s. o.

C-1

...... d*la:llv*.......

C-1 None NIA N//\\

.. Ml lnqm:I *ad1H1lonal

.Pl119 llelcctlve lubes C-1 Nona lS 1ubc1 In 11111 S. O.

• c-2 and ln111ecl addlllonal C-1 l'lug d1:lcctlvc lubes 45 1ubt1 In 1hl1 5. 0.

Perlorm Kllon lor C-l C-l result ol Uni um11I*

Pcrlorrn ectlon lor C-J C-J *csull ul llr11 N/A NIA uma1la C-J ln1111:d 111 lulie1 In All ollMlf thlt 5. G., plu1 de*

s. 0.1...

Non*

NIA N/A lcclive l11be1 ~..a ;

C-1 ln11acc1 25 lulaet lei Som* S. G.1 Pcrlonn ec:llon lor NIA NIA c1tll othc* 5. O.

C-1 bul no a1Lll1lon1I C-'J 1e1ul1 ol aeconrl l1e111pl ho1lllca1lo 11

.. mp..

s.o....

to NftC 1t1111111ql C-l lo --

Acldillonal i~,.,

ln1pec1 *II 1ubc1 In c.FA.:>O-?a

5. G.11 C-J HCh s. G. Ind......

0crd 1oc.i:tt 50.711 delcctlve 111ltc1.

s ctpt>/icA~le.. ) ---

Pt lllftlll Jlo1Uk11lon "N/A NIA NRC p1111111n1 IO lllHillHlhlR 5

• J ~ 1C. Whcr* N h the numhet ol 11e1m uencnton In the emit. *ricl n h the nuanb11 ol aleam 9e11cu1m1 l11111ccltd n

dm lo!J *n l11111ecll11n "Alternate nctlon 1nay be used Jn accordance with parngrnph (s,e ne><t poqe)

J

~EACTOR COOLANT SYST!.'4 S?EC~F!C ~CT!'l!i'f LIM!T!NG CONO!TION FOR OPERATION J.4.S Th* sp.cif1c activity of th* primary coolant sn111 b* lim1ttd to:

a.

!. 1.0 ~C1/gr11111 COSE EQUIVALENT I*131, and 1:1.

!. 100/!' ~C1/gr~

APPLICABILITY:

MODES 1, 2, 3, 4 and 5 ACT!ON:

MOOES 1, Z and ~

cr;==:;un tne seeeH4e aethHy e¥ 11111 5P1ui&l"y ""'1i.?J$

• lad.C1/9,*i. °-

--..._, BeSE E$H\\'1'iLEH1 i Ul a-.t; *itMl'i the al1&*.::~1e 141114' (eele..

\\ and ee Utt 1 e<t eat1 et.e 111'11) 9;.e~ '" 1"'191:1P\\ J. 4 1

• oer1 i:i e,.

'1 "'IY Hl"C; AWi ta, W5a ;; 48.,.,, iia'N'd1 Hi tFIU HiPU1 lfll WAill"

' !Mii llNlilll~l'iHS 5~111,... IMHli 1Q ** ? Hft'e: af e... -~"* t

/11u1 y11,1y 85alF'UiR9 ;111111.

r~. llN¥15hAI,, ~-*"1'1*Ui~l'I J ll.9.1 a... l'iU U51liHlh!./...-

'-'1th tht sDtcHic activity of th* prin\\11,*y coola11t > 1.0.Cf/9r!m OOSE EQUIVALENT I-131 for mart thin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during on* con*

tinuous ti1111 fnttrv1l or excffdinc; th* limit.1 tnt shC'fft on

~~~~ ~-~~~;.,~* in aL least HOT STi\\NDBY with ravg < soo*F With tht specific activity of the ?~imary coolant > 100/!'

~Ci/gram, be 1n 1t least HOT STANDBY with T1 9

< soo*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

v MOOES 1, 2, 3, 4 and 5

a.

W1tn tn. SP9Cif1c activity of th* pPi1111ry coolant> 1.0 ~Cf/q~am COSE EQUIVALENT I-131 or> 100/r ~Cf/gram, per1orm tht sampling and analysis,..qu;rements of it1111 ~of Table 4.4-2 until tnt

~~:~;~~~!;:~~~~!~::~:~~~~~~~~

..,..; tn t avg !. sod"F.

SALEM

• UNIT 1 3/4 4-ZO

~*-

L. -

REACTOR COOLANT SYSiEM l,

~e1Gt;P 111;w1F

~i&t;Fy &t1Fti~9 4i ~;wPs ;PieP te tP'le fiPH 5Hl!'le iiq,,.,,.ie;ii t"* li"'it wu e-'teeeded,

a.

li'w1l QWFAWlll ;y,;,. r=egi ;i:i I

3.

Gleal'I ~" fle~ ~iUeP"y !taP"til'I* ~ ~e~,.,. l'P"ieP" te 1!1'te fir!t

&illl~ll iA wAi;R CAI 1 i111it WH e:iteeed1d1 4,

HhteP"y. ef de gas9il'lg e19ePUiel'IS1 if Ul¥1 9!artil'llJ 48 i'letsM lllFi'QF ;; tAI f i FU SM'l e i" w~i &" '"e l i111H *U exceeded,

• ~ *:.

. *~....

I 11 i.

'~.

SU!lVEILLANCE ~EQUIR~~.f.1"15 4.4..8 "'the sptcif1c activity of the primary coolant snall be.deter.nined to be,..,~,thin: the.1.imits by r;>erfof'!'Mnce of. the sampling and analysis program. ~1***r ~o 1 i

• 4". 4--4

• SALEM -UNIT 1 3/4 4-21

3.5.l.5 The stM.Zc~ural fnt11ricy af th* c~ncafnman: sh*i1 :1 ~*i~tl~~t~

at & l1v1l cons1stan: wit.~~* acc1~t~c1 cri:ar1a 1n S~~1~~c:a:~cn ~.:. 1.:.

ACi!C~I:

.:..S.1.5.1 C:rT:1!~1!'!: Su~!c!s

~.,, s-::-Jc:~r!l tr:t~:-~:-i -:~ :.:.:a ~;:~!*:

ac:1ssiat1 tnt1riar ana ax:eriar s~ri'!cas af ~~* c:ntafr::e.~~. t~:l~:~~;

the l 1ntr ;:ih.:1, Sl'lil l ct dlte~'inld :l.lrin; t!'!1 sm..t:C"..-n

~.=r ~::: ~/:!..:.

.--n*"'f-a.. - *a.a!c".. I -s** *as* (-*~.....,.c* ::c-~Jf.-s*~.. n ' = T ~* -..,.a llli* i6* '*-**:

I

• iii****~.. ---.1 '--***

.... *-t *.

visual il'Tsoe-:-:~c:i :f :~es! surlacu.

i"!'!~S ir:i:a-::-:::i s~aii :1 :a!""':~!*:

~'r'1Qr- :: ~::1 ';".!!;. :::-::!~~!~: 1a!:,1;1 ~!':! :11: :: *:!!9~:':t cn1~;1s ~r:.1~;aa:-1r:c1 ~:-

=~~sr-

!b::c~!: *:r;r-?!1:~:~.

.*-~ -s~-

~.:. 1 * :

• Z

~*~e~s

~rPJ !C~~~a 1 ~..;?9!~!:~ =~ *:f :~! :::-: :1 ~ ~*r.-: I-:~*.;:~*.;-:

Cit&:~ ~~rH:; :.-:a lCOVI r1~ t rK f ns:K~i a:1s Sl'.14 ~ 1 C:I/,.tHP'Yti ?!! ?.*!

~

A I

.a I S!': ! ! ~

~ ~:;...: !

a descri~t1:n af ~* c::ia'f:ion of ~l'I* c:nc:-w:a, :::1 1ns:e -:~::: ;:-::!': *. *:.

t."la t=lerancu an :ncking, and c.,. c:~:1'1i ac::i i:n tll<

i

--~~-

• jfi

~*

e.vAl"-ttfecl For re{"'r-fc../o;/dy pc.trsu~nf -tl:>

lOC. rR. 50. 7 "J.. cvio/ /OC.JIKR t)O. 7 3. 71,e e ib.l~4f1°"'1

~ho. t I be d~c.e,r'I G',, t ta/ o..;io(

. 1* **

RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The.dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

b.

During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, i~ lie~ ef a LieeAsee gveAt ~e~er;~ prepare and submit to the Commission within 30 days, pursuant to Specification 5.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b.

The provisions of Specification 3.0.3 and J.0.4 are riot applicable.

SURVEILLANCE REQUIREMENTS 4.11~1.2 Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.

SAL£M - UNIT l 3/4 11-5 Amendment No. 59

RAO!OACT!VE EFFLUENTS LIQUIO RADWASTE TREATMEN~

LIMITING CONO!T!ON ~OR OPERATION 3.ll.l.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials lfqufd wastes prior to their discharge when the projected cumulative doses due to the liquid effluent from each reactor to UNRESTRrCTEO AREAS (see Figure S.l-3) exceed 0.375 mrem to the total body or 1.25 mrem to any organ during any calendar quarter.

APPLICABILITY:

At all times.

ACTION:

a.

With the radioactive liquid waste being discharged without treatment and in excess of the above limits, iA liey af a biaeAsee i'.veAt ~eiaertr prepare and submit to the Conunission within 30 days pursuant to Sptu:ification 5.9.Z a Special Report that includes the following information:

l..Exp,lanation of why l fquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.

z. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3.

Summary description of action.( s) taken to prevent a recurrence.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicab1e.

SURVEILLANCE.REQUIREMENTS 4..11.l.3 Oases due. to liquid releases sha11 be projected. at 1east once per 31 days in accordance with the ace~.

S:.L.:~ - UNrT l 3/4 l l-6 Amendment Na. 59

RADIOACTIVE EFFLUENTS DOSE -

~OSLE GASES LIMITING CONDITION FOR OPERATION 3.ll.2.2 The air dose due to noble ga$eS released in gaseous effluents, from each reactor unit, from the site areas at and beyond the SITE BOUNDARY (see Ffgure 5.l-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

b.

Our1ng any calendar year: Less than or equal to 10 mrad for ganma radiation and less than or equal to 20 mrad for beta radiation.

AP?LICABILITY:

At all times.

ACTION:

a.

With the calculated air dose fran radioactive noble gases in gaseous effluents excee<iing any of the above limits, iA lie~ ef a ~ieeAsee SveAt Re~;Fif"prepare and submit to the Commission within'30 days, pursuant to Specification 5.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions*

that have ~een taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in cql!ll'liance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SUR~EILLANCE REQUIREMENTS 4.ll.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year shall be detennined in accordance with the OOC~ at leas!

once per 31 days.

SAL~:-! - UN[T l 3/4 11-12 Amendment

,'~o. 59

RADIOACTIVE EFFLUENTS*

DOSE - IOOINE-131, TRITIUM, ANO RAOIONUCLIDES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The.dose to a MEMBER OF THE PUBLIC from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents.released, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Fi~ure 5.l-3) shall be limited to the fol 1 owing:

• a. During any calendar quarter:

Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY:

At all times.

ACTION:

a. With the calculated~ dose from the release of iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, iA lie~

ef a LieeAsee EveAt Rejiert(prepare and submit to the Commission within 30 days, pursuant to Specification o.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent release~ will be in compliance with the above limits.

b. The provisions of Specifications 3.0.3 and 3.0.4 are* not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, tritium, and radionuclides in particulate form with ha lf-1 i ves greater than 8 days sha 11 be determined in accordance with the OOCM at least once per 31 days.

SALEM - UN IT l 3/4 11-13 Amendment Na. 59

RAD!OACT!VE EFFLUENTS GASEOUS RAOWASTE TREATI1ENT LIMITING CONOITIOA FOR OPERATION 3.ll.2.4 The GASEOUS RAOWASTE TREATMENT SYSTEM and the VENTILIATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from the site to areas at and beyond the SITE BOUNDARY see Fi ure S.l-3.exceed 0.625 mrad for ganima radiation and 1.25 mrad J

for beta radiation in any calendar quarter. The VENTILIATION EXHAUST T"REATMENT SYSTEi~ shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure S.l-3) would exceed l.875 mrem to any organ in any calendar quarter.

APPLICABILITY:

At all times.

ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, 1R liew ;fa ~1'8RSH EveRt ~eport._. pr:epare and submit to the Conmission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

l. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason far the inoperability,

2.

Action(s) taken to restore the inoperable equipment e~~;~~eAt to OPERABLE status, and

3.

Summary description of action(s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.4 are not applicable.

3.0. '3 and SURVEILLANCE REQUIREMENTS 4.ll.Z.4 Oases due to gaseous releases from the site shall be projected at leas~ once per 31 days in accordance with the OOCM.

S,:1.L£~ - !JN[i l 3/<1 11-l.1

.~mendment No. 59

SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION

---

~----------------------------------

3.11.3. The solid radwaste systel'I shall be used in accorrlance with a PROCESS CONTROL PROGRAM to process wet radioactive waste to IT1!et shipping and burial ground requirelT1!nts.

APPLICABILITY:

At all times.

ACTION:

a. With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively pack~ged solid radioactive wastes fro"" the site.

b.

The provisions of Specifications 3.0.3 and 3.0.4/<aAe 9,9,1,9,e are not applicable.

SURVEILLANCE RECUIRE~ENTS 4.11.3. The PROCESS CONTROL PROGRAM shall he used to veri*fy the SOLIDIFICATION of at least one representative test specirTP.n fr~m at least every tenth batch of each type of wet radioactive waste (e.g.~ filter sludges, spenf. resins, l1J evaporator bottoms, boric acid solutions, and sodiul'I sulfate solutions).

a. If any test specilTll!n fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such tir.-e as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be** deterr.ti ned in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.

SOLIDIFICATION of the batch Play then be resurred using the alternative SOLIDIFCATION parameters deter~ine~ by the PROCESS CONTROL PROGRAM.

b.

If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM s"all provide for the collection and testing of representative test-specimens from each consecutive batch of the sarre type of wet waste until at least three consecutive initial test specirrens de1TDnstrate SOLIDIFICATION.

The PROCESS CONTROL PROGRAM shall be l"Odified as required, as provided in

• Specification 6*13, to assure SOLIDIFICATION of subsequent batches of waste.

SALEM - UNIT 1 3/4 11-17 Amendment No. 64

RADIOACTIVE EFFLUENTS 3/4.ll.4 TOTAL DOSE LIMITING CONDITION rOR OPERATION 3.11.4 The annual (calendar year) dose or dose commitment to any MEMSER OF THE PUBLIC, due to releases of radioactivity and radiation, from urnaium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ (except th~ thyroid, which shalt be limited to less than or equal to 75 mr~).

APPLICABILITY:

At all times ACT!ON:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding t~ice the limits of Specification 3.ll.l.2a, 3.ll.l.2b, 3.ll.2.2a, 3.ll.2.2b, 3.ll.2.Ja, or 3.ll.2.3b,

-.alculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the limits of this Specification nave been exceeded.

rf such is the case iR lieY ef a lieeAsee E*JeAG Re!i&l"t, prepare and submit to the Commission within 30 days, pursuant to Specification 5.9.2, a Special Report that defines the correcti~e ai:tion to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and inc.ludes the schedule for achieving conformance with the above limits. This Specical Report, as defined in 10 CFR ?art 20.405c, shall include an analysis that.estimates the radiation exposure (~ose) to a MEMBER OF TI4E PUBLIC from uranium fuel c:ycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report.

It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

tf the estimated dose { s) exceeds the aoove *1 i mi ts, and if the re 1 ease condition resulting in violation of 40 CFR ?art l90 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part l90.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

S~L::~ -

iJ.'l [i 3/'1 ll-18 Amendment

~io. 59

3/4.12 RADIOLOGICAL ~NVIRONMENTAL MONITORING 3/4.12.l MONITORING PROGRAM LIMITING CONDITION -FOR OPERATION 3.12.l. The radiological environmental monitoring program shall be conducted as specified *in Table 3.12-l.

APPLICABILITY:

At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in T:able 3.12-l, 1R liey af 1 l.i;aR&H E11aRt, ReJ'e~ 1.prepare and submit to the Cammi s s ion, in the An nu a 1

~ogical.Environmental Operating Report required by Specification L!J 6.9.l.~. a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the level*of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, 1 A 1i ett ef a Li eeAsee S*:eRt Re~eFtf" prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potent i a 1 annua 1 dose to* a MEMBER OF THE ?UBL IC is less than the calendar year limits of Specifications 3.11.l.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall l;)e submitted if:

concentration (1) reporting level (l)

+

concentration (2)

• reporting level (2)

+ *** >l.O When radionucl ides other than those. in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a member of the publi.c is equal to or greater SALEM - UNIT 1 3/4 12;-l Amendment No. 59

3/~.lZ RAOrOLOGICAL ENV!RONMENTAL MONITORING 3/4.lZ.l MONITORING PROGRAM LIMITING CONDITION FOR OPERATION ACTION:

(Cont'd) than the calendar year limits of Specifications 3.ll.1.2, 3.11.2.2, and

• 3.11.2.3. This report 1s not required if the measured level of radioactivity was not the result of plant. effluents; however, in such an event, the condition shalt be reported and described in the Annual Radiological Environmental Operating Report.

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, ident1f~ locations

• for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

I A l i eij ef a li eeAsee E>rer:rt R ap0rt aAd Jursuant to Spec1 f1 cation fli1 __

6.9_,.__~, identify the cause of the unavailability of samples and the l.!.J--newTOcation(s) far-obtaining replacement samples.in the next Semiannual Radioactive Effluent Release Repor-t.

Include in the report a revised figure(s) and table for the OOCM reflecting the new location(s).

d.

The provisions of Specifications 3.0.3 and 3.0.4 are *not applicable.

SURVEILLANCE REQU!REMENTS

<1.12.l The radiological environmental monitor-ing samples shall.be collected pursuant to Table 3.12*1 fran the locations specified in the OOC~ and shall be analyzed pur~uant to the requirements of Table 4.lZ*l.

- SAL~:-!

• U~HT 1 Amendment No. 59

Vl

~

r ***

w -

N

• 00

• ~

ID

J tt,.

J rt

~

0.

l.H

• U TA-.12-2 MlPOMllNG LEVELS FOM MAOIOACllVllV COHCENIAAflONS IN ENVIRONMENTAL SAMPLES Reporting levels 11-1 Hn-54 Co-58 Co-6f) ln-6!>

lr-Hb-9!>

I-Ill Cs-114 Cs-111 M.ter (pCl/0 2

• 10*(**

I x lOl 4

• 102 I x 1101

]

• 102 l * *102 4

• 102 2 (b) 10 50 2

• 102 Airborne P*rtlcul*te or G*ses (pCt/al)

I 0.9 10 20 fhh (pCl/Kg. wet) l

• 10*

I x 104 l

• 10*

I

• 10*

2

• 10*

I x 101 2

• 101 Hiik (pc111a l

60 10 l

• 102 food Products (pCl/kg. wet)

I x 102 I x 101 2

• 101

0.

(*) for drink Ing w*ter umples. Thh 15'10 CfA Put 141 v*lue. I+ flo olr1ri,~;,,')

~Q f-er,~Hwa..y.

e,,5fs I

0.

~Qf~e o-F

~ x. 10 '{ f C.; /..1 l"JO.r 6e UG~o(.

{le,) For dr1,., ~:nj WOi: fer S4P1.ples.

"1°(~'5 rs

~

wo.f.er pc.rft111a'(

t!!..j<","5fs,

a.

~lue o-F

'(O CFR. Pctrf-JI/(

'"'/we. J:F no drlnlii;Yi:J

';20 f C;/..f /t'li:l/ be u,ecJ.

VI

)...-***

~

c 2......

--t UI

'° Analys h 11-l Hn-54 Co-5U, 60 ln-65 lr-tth-%

1-lll Cs-l13 Cs-l11 P.t-l.a-l40

~

W1ter (pCl/0 2ooJC:

15 JO 15 JO I !a

~

p 15 18 15

• J TABLE 4.12-1 HAUHllH VALUES FOR THE LOWER LIMITS OF DETECTION (uol<l~J Atrborne Pirltcuiate f hh Ht lk food Products

... Sedt.ent

• or G1ses (pCI/* )

(pCt/Kg, wet)

(pCt/I)

(pCl/Kg, _wet)

( pC I /Kg, dry )

l

• 10-2 130 260 130 260 1

• 10-2 I

liO 10-2

• I ~

a~o.

5 ll llO 15 60 6 IC 10-2 150 18 80 IOO I

15

~

TABLE 4..12-l (Cont'd)

TABLE NOTAT:ON f

tn rmc1uminescent dosimeter~ used for

• a ~e<:;uired detec!io'n capaoi11t1es ;o;n ;~ ~e9ulat~ry Guide 4..13, Rev. l, July environm1nta1 mtasu~ements a~e g v l977.

o The L~O 1s define4j 1n Taole 4.ll-l.

c u.{J f;,..

clr;.~,4;;ij Wet.fer

~,#f1k~. r-F no clr.*n,4*,*11j ~fe,-

fq ~~7 ex,*;, ti, c...

/c/<1e o -F 3000 p C,;./.f

/l'la_y foe

'<~e/.

J llD J=;r dr~l\\~,-,,J w~l-e.r t£:,a-iples. ::C-F

{lo dr~t~I/\\~ w~ IP, pctti<.J~,v er is~

Cl v~l'<P

°' F 10 f' c..; /.P _,qt 6e ut:.~

~me"cme"t ~c. :~

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LANO USE CENSUS LIMITING CONDITION FOR OPERATION

---

~---------------------------

3.12.2. A land use census ~11 be conducted and shall identify within a dista;;cc: of S ~m {5 ::ilas)...,c; location in each of the 16 meteorological -sectors of the nearest milk animal,, the nearest residence and the nearest garden* of greater than SO m2 (SOO ft') producing broad leaf vegetation.

(For elevated releases as defined in Regulatory Guide l.lll, Revision l, July 1977, the land use census shall also identify within a distance of s km (3 miles) the locations in each of the 16 meteorological sectors of. all milk ani1T1als and all gardens of greater than SO m2 producing broad leaf vegetation.

APPLICABILITY:

At all times.

ACTION:

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.ll.2.3, iA lieY ;fa ~1GeRsee iveAt ReiaeFt, identify the new location(s) in the next Semiannual Radioactive*

Effluen~ Release Report, pursuant to Specification 6.9.l.)1~

b. With a land use census identif~ing a location(s) that yields a calculated dose or dose.cormJitrrent (via~ the sa1T2 exposure patnway) 20 percent greater than at a locatian from which samples are -currently being obtained in accordance with Specification 3.12.l, add the new location(s) to the radiological environl'1ental r.tlnitoring program within 30 days.

The sampling location(s), excluding the control sta:ion location, having the lowest calculated dose or dose commitnent(s) (via the salTI! exposure_pathway) may be deleted from this rmnitoring program after~October 3lQJof the year in which this land use census was conducted.

In 1 ie~ of a Lice~see E *errt Report and ~ursuant to S ecification 6.9.l

, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure(s} and table for the OQCM reflecting the new location(s}.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

~road leaf vegetation sal!lllling of at least three different kinds of vegetation may be perfor1T1ed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted 0/0 in lieu of the garden census. Specifications for broadleaf vegetation sampling in Table 3.l2-l.4c shall be followed, including analysis of control samples.

SALEM - UNIT l 3/4 12-11 Amendment No. 64

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.tZ.2 LANO USE CENSUS (Cont'd)

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing s~ason at least once per 12 months using that 1nformation that will provide the best results, such as 'r:ry a door-to-door survey, aerial survey, or by consulting 1oca1 agricultur.e authorities. The results of the land use census shall be inc1udea in the Annual Radiological Environmental Operating Report pursuant to Specification 0.9.l.~

S~L~M - UNIT l 3/4. 12-12 Amendment ~lo. 59

-.or.

RADIOLOGICAL ENVIRONMENTAL MONITORING

.3/4.12.3.

rNTERLABORATORY COMPARISON PROGRAM LIMITING CONOITlON FOR OPERATION 3.lP.3

~nalyses sha11 be perfoimed on radioactive mJteria1s supp1ied JS pJrt cf an Interlaboratory Ccmpar}son Program which has been approved by the Commission.

APPLICABILITY:

At all times.

ACT!ON:

a. With analyses not being performed as required above, report the co.rrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.l.~

T1.l

b.

The provisions of Specifications 3.0.3 and 3.0.4. are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required Interl ab.or-atory Comparison Program and in accordance with the ODCM sha 11 be included in the Annual Radiological Environmental Operating.Report pursuant to Spec Hi c.at.1 on 6.9. l.fu.

SALEM - UN IT 1 3/4 12-13 Amendment,'lo. 59

REACTOR COOLANT SYSTEM BASES 3/4.4.5 STE.il.M GENERATORS (Continued)

Wastage-typa defects are unlikely with proper chemistry treatrnen~

of the secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations. Plugging will be required for all tubes with imperfections exceeding the plugging limit of 40~ of the tube nominal wail thickness.

Steam generator tube f nspections of operating plants have demonstrated the capability to reliably detect degra¢ation that has penetrated 20~ of the original tube wall thickness.

ev~lv.a.fed -For repor~b;/;iy Whenever the r.esults of any.steam generator tubin specti on fa l1 into Category C-3, these resu 1 ts wi11 be~llMMl-¥--f'"e!Mi'~d-to the Commission pursuant to Secfio11s 3/4.4.6 REACTOR COOLANT SYS'i'EM LE.il.KAGE 3/4.4.6.1 LE.il.KAGC: OEiECTION S'fS~MS and toe.FR t;b. 73, The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure ~oundary. These detection systems are consistent with the recommendations of Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Oetection Systens", May 1973.

• 3/4.4.6.2 OPERAT!ONAL L~~KAGE I.ndustl"y experience has shewn that '"'i'lile a limited amount of leakage is expected from the RCS, the unidentifiea portion of this leakage c~n :e reduced to a threshold value of less than l GPM.

This threshold lfalue is sufficiently low to ensure early detection of additional leakaae.

The 10 G~M IOENT!F!EO LEA!<AG~ limitation provides allowance for a 1 imi ted amount of 1 eakage from known sources whose presence wi 11 r.ot interfere with the detection of UNIOENTIF!EO LEAKAGE by the leakage detection systams.

l SAL.S\\1 - UMIT 1 a 3/4 4-3

REACTOR COOL~'{i S'fS'i!M BASES 3/4.4.a Si'!CIF!C ACTrlt7'f Th* lfnrttat1cns on thi sp.c1ff c ac:-:1'11~ o'f eh* i'ritr.al'""/ c:ohnt 1nsurt that the resulting Z haur doses at :.,1 sita ocund1ry wil1 not 1xc1ed an appropr11taly s~11 fraction of ?!rt 100 111111:3 folla~1nq a steam g1n1r1tcr tuct l"'Jptur-9 1c:1 dant 1 n canJunc:t1 on...,1th !n asswr.&d steady state pr1mry-ec-saccnda1""/ st11111 ;1n1rucr l uk1~* nt1 ai' 1. Llel GPM. in* values for th* limits on s,pec1fic ac'C'tvity r"'9Prts.,,t 1n't~-a.;;;.J T 1m1 ts bas~ upan I ::l&r:matr1 c: 1111 l ua t1 on by :tit 1'IRC o1 t'/'1 c1 l s1 ta locations. intsa values are ccns1r11t1v* in that specific sit* ~1rui-1t1rs o1 th* S.l1111 si:a, suc.i as s1t* oaundal'""J toc:1tion and ~.eta~rolag~

~1 ccnd1t1ans, were not cans1dtl"'ld in this 1v1lu1tian. int ~RC is ffnalf:1n; s1ta specific cl'"'!t1r11 wn1ch w1ll ot us~ as t."11 oasis for th* 1'"99Ylluat1on of tne specific activity limits of ~i1s Sita.

~his re9Y&luat1on may result in higher l1m1:s.

n. Ac+tQM UH:llfte1'11 ~*"""'"'"' PGWER "QPEAATIOH ee ea.. 11A1;11 f!Jf'

.Hm:ftae tiM ~ePiees w1~ ~* 19,.;,,.P')* eeela1t1' s Siilteif1e ae1ivily a. T.9 "C1/g1!111 QQH iQl.lt'J.e.U)IT t 11' I'll witit1111 ~* Jllewull lilll=i~ SAe'HA 9FI

~fi\\lP4 3,4 t, !GGSRReeailS ~essial1 fe41AI sei(1Rg ~~~ell!9"e" *Ai:~ may

cc;.,r f;l lQwi Af IRIAIJIS f A nig.ei_YJ.L ?GWS~. GUPI e

i EIA 1-Hil 5~1G1f1 G ael=f*31gy levels IJlGH81A9 l.Q l;&'f/pam QC.Si iQUt,IA~ t*lll :u-: 1*i":::tii:t ta* l illli u si!Gwlt EIA Fi...... 3. "'"I llft:IS't ~* l"ln.--1 eud '!S AQ ~.. ~IA la ~*P"e9l'l1,., ~* Wl1~' 9 111rly 9!'1Plfli119 11N 91,.H tl-11 H'l'h'i ;y lt*Jels al111'11te ay F1tu.. la4*1 iAG1"9!51 ~,. ' AGWP tl!i~1; QQll a; ;n, s*ta aeuAaal'f ay I flGCIP e# WP ti 3Q fe11ewiA9 i p9S1Wll~8 cia111 $1RIJ"4t;~

tfilaa ""4Jl1W*.

~uc1n9 T1 ta cSQQ*F ?r9Yll!f1CS Chi ~!19!SI of !C~1vit1 sr.ould I staur gen1i-1Qr Ube r"J!'tU1"'9 since ~.,e s*t1.1r1tian ::r9uur-! of i:.":e :ir1:::ar:1 c:olant is ~low the 11 ft ar!ssur! a'T' c.i,1 atmesohe!'"'ic stum.,1 i af *1a: 1u.

ine su,..11iilanca r-9<1uirentnts p~vid1 !dequata us-.r-!nc:! :::at ex:!ssi'le s~tc1f~c act1vity 1ev1ls fn tht ~l"""fmary caolant wiii ~* :e'!f_c~_J_~ _ _.!fft su11icient c1mt t.= :akt ca~c~1vt !cticn. !nforma:ian oat~

i od f ne spi lei ng wi 1 l bt used t.= assess tht ~arln'Atar~ as sec ia cad *..-'i ::-i sp11c1ng ~nenaana. A l"educt1on 1n f'l"'!Cu1ney of isat:!:lie ar.al:r-us f:1;c*.¥i!'!i;

~awe~ c~anqts may ct pe~ssibie 1f Justified by cne aata ee~ainec.

3 !/! <L-3

6.1.l The General Mar.ager - Sa'.em Ccera:;O"S sra;; :e resocrs':"e --~ :.~~~

facility operation and snail ae'.egate, in writ~ng, :-e suc:ess'::ri ::: :-*s responsibility during his aosence.

6.l.2 The Senior Nuclear Shift Sucervisor, or during Mis aosence fr~m :~e control room a designated inaividual, shall oe responsible for ':!"le contr::

room command function.

A management directive to this effect. signed ~Y :-e Vice ?resident and Chief Nuclear Officer, shall be reissued :o a11 s:atlori personnel on an annual basis.

6.2 ORGANIZATION 6.2.1 ONSITE AND OF~SITE ORGANIZATIONS Onsite and offstte organizations shall be established f~r ~nit ocerat~oM a~:

corcorate management. resoectively.

The onsite and offsite organizatiors shall include positions for activities affecting the safety of the ~uc~ear

• ower plant.

a.

Lines of authority, responsibility, and communication shall be established and definea from the highest management levels throu~n intermediate levels to and including all operating organization positions.

These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationshi~s. ar.c job descriptions for key personnel positions, or in eouivalent *orms of documentation.

These reouirements shall be documented in t~e Salem Updated Final Safety Analysis Report and updated in accor:an:e with 10 CFR S0.7l(e).

b.

The General Manager - Salem Operations shall be responsible for overall unit safe operation and shall have control over tnose ors':e activities necessary for safe operation and maintenance of tne plant.

c.

The Vice President and Chief Nuclear Officer shall have corporate responsibility for overall plant nuclear safety and shall ta~e any measures needed to ensure acceptable performance of the staff iri operating, maintaining, and providing technical support to the o~ar.:

, to ensure nuclear safety.

d.

The individuals who train the operating staff and those who carr; out health physics.and ouality assurance functions may report :o :-e appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from opera:'-;

pressures.

6.2.2

~ACILI:v STAFF The facility organization shall be subject to the following:

a.

Each on duty shift shall be composed of at least the minimum sni~:

crew composition shown in Table 6.2-1; SALEM - UNIT 1 6-1 Amendment No. 99

ADMINISTRATIVE CONTROLS FACILITY

b.

c; I et.

STAFE (Continued)

~~

r<:ea.c 1or-At lea*t one licensed Operator shall be in the control room when fuel i* in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the Control Room area at all tille*.

the reaecer.

ALL CORE ALTERATIONS shall be ob*erved and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during thi* operation.

A site Fire Brigade of at least 5 member* *hall be maintained onsite at all times*. The Fire Brigade shall not include 4 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other es*ential functions during a fire emergency.

The amount of overtime worked by plant *taff members performing safety-related functions must be limited in accordance with the NRC Policy Stacement on working hour* (Generic Letter No.

82-12).

The Operating Engineer, Senior Nuclear Shift Supervisors, and Nuclear Shift Supervisors shall each hold a senior reactor operator license. The Nuclear Control Operators shall hold reactor operator licenses.

~~*

The Operations Manager shall meet one of the following:

(1)

Hold an SRO license.

(2)

Have held an SRO license for a similar unit (PWR.).

The Aealca pnyaiQa ceeAaieiaa &Rd Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.in order to accommodate unexpected absence of the ~eailA pl!l;rsiu UeAaieie &Mfer Fire Brigade members provided immediate action is taken to restore the 'Aealcn phy11iQ* CHaahiMl &RC!/ec Fire Brigade to within the minimum requirement*.

SALEM

• UNIT 1 6-la Amendment No. 110

Figur~ 6.2-1 CORPORATE HEADQUARTERS ANO OFF-SITE ORGANIZATION FOR MANAGEMENT ANO TECHNICAL SUPPORT (Deleted)

SALEM - UNIT 1 6-2 Amendment No. 99

FIGURE 6.2 - 2 FACILITY ORGANIZATION (Deleted)

SALEM... UNIT 1 6-3 Amendment No. 99

PtOP ~

r~sL:: s.2-1

~!N!MUM SH!Fi C~E~ CCMPIJS!i!CN SAL£~ !JN! T l

.,.il!iH UNlT 2 IN

~ODES S lJR 6 JR OE-FUELE:D POSITION NUMBER OF !NO!V!OUALS KEOJIRED iO F!LL

~OS~7:0N MODES l, 2, 3 & ~

1"10DES 5 & 6 SNSS la la SRO lb none STA lb none 1'iCO 2

l EO/UO 3

2c Mai o:teaacce El ect~:i c:i ao l

ClC Cl!

At)p: l R~. Pro. Tea.#i11.t:.lt4r'I

, a..

14;e.l WITH UNIT 2 IN MODES l, 2, 3 OR 4 POSITION NUMBER OF INOIVtoUA-LS REOHREO TO FILL POSIT!lJN AoD:

!I 91 Si

~

I e/

SNSS SRO STA NCO EO/UO MOO ES l, 2, 3 & 4 ia lb lb 2

3d ia I a.

Individual may fill the same i:;nsition on Unit 2

.~OES 5 ~ 6 ia

~ne

~ne l

l n

,~

tndividual wrc fulfills the STA requirerrent may fill the sa!T1! position on Unit 2.

ine STA, if a licensed SRO, may concurr-em:ly fill the SRO ::csition on one unit; the other unit also requires a qualified SRO on shift.

One of the t'~ required individuals may fill the ~sition on Unit 2, such that ti'lere are a total of three EO/UO 's for ooth uni ts.

One tlf the three required indiviriuals may fill the Sal'!e pasition "Jf 'Jni-: 2, such that there arP. a total. of five EO/UO's for both units.

tJo+ nsedeol tf" ~of/, rea&fors a.re de--H.eled.I SALEM - UNIT l 6-4 Amendment No. 62

SNSS SRO NCO STA EO/UO TABLE 6.2-1 (Continued)

Senior Nuclear Shift Supervisor with a Senior ~P.actor Operator License on teen units.

Individual with a Senior Reactor Operator License on t:oth units (normally, a Nuclear Shift Supervisor ).

Nuclear Control Operator ~itn a Reactor Operator License on both uni ts.

Shift Technical Advisor (if licensed as SRO, may be assigned duties as a Nuclear Shift Supervisor).

Equi p*nt Opera tar or Uti 1 i ty Operator.

Except for the Sen~or Nuclear Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-l *for a period of time not to exceed Z hours in order ta accol11!T1ldate the unexpected absence of ~n-<luty shift crew rrel'Tbers provided tl'lat irmrl!diate action is taken ta restore the Shift Crew Col'Tf'Qsition tc within the Mini.rum requirements of Table 6.2-l. This provision roes not per1"'it any shift crew ~sition tc be unmanned upon shift change due to an oncoming snift crewperson 's being 1 ate or absent.

During any absence of tl'le Senior Nuclear Shift Supervisor from the Control Room area ~hile the unit is in any MOOE, an individual with a valid SRO License snal 1 be designated to assu1te tl'le Contra 1 Room command function.

SALEM

• UN IT l 6-5 Amendment No. 62

ADMINISTRATIVE CONTllOLS 6.2.3 SHIFT TECJINICAL APVISQR 6.2.3.l The Shift Technical Advisor shall serve in an adviaory capacity to

~Shift luperviaor on matters pertaining to the engineering aapects assuring

~

safe operation of th* unit.

6.2.3.2 'nl* Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with apecific training in plant design and respon.e and analyaia of the plant for tran.ients and accidents.

6.3 [ACILIIY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI Nl8.l-1971* for comparable poaition. and the supplemental requirement* specified in Section. A and C of Enclosure l of the March 28, 1980 NRC letter to all licensees, except for. the Radiation Protection*ER&1R*** who shall meet or exceed the quali ications of Re latory Guide 1. 8, September 1975.

the i,,J;.,.;Juo.f Jesi"$t1ttfeol a.s 6.4 nAINING 6.4.1 A retraining and replacement training progra,m for the facility staff shall be coordinated by each functional level manager (Department Head) at the facility and maintained under the direction of the Manager - Nuclear Train1sng and shall meet or exceed the requirements and recommendation. of Section 5.5 of ANSI Nl8.l-1971 and hppen~ix 'h' ef 10 CFR. Part 5~ aa* Gae s1:1pplemeneal re~~iremeRt* speeifie* in Seetiena A an4 C ef Eneles\\R'e 1 ef tae Marek 28, 1989 NR:G letter te all lieetMees, and shall inclYd* f.. 111ar1matien with relev&RC in~scry eperacienal 1Kperienc1.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager - Nttelear Training and shall meet or exceed the requirements of Section 27 o FPA Code-1975, except for Fire Brigade training sessions which shall be hel at least quarterly.

~~ie Ft-o+ec.fiori The Operations Manager shall meet one of the following:

(l) Hold an SRO license.

(2)

Have held an SRO license for a similar unit (PWR.).

SALEM - UNIT 1 6-6 Amendment No.110

6.5 REVIETJ AND AUDIT 6,5,l SIAIION OPERATIONS REVIEW C0!1MITTEE CSORC2 fUNCIION 6,5,l,l The Scacion Operations Review Cornmiccee shall function co advise

~e General Manager - Salem Operations on operational maccers related co nuc:,ear

safety, COMPOS II ION 6,5,l,2 The Station Operations Review Committee (SORG) shall be composed o:*

~=t: :r.vt;eer 10 '* 0.1. "l MK~e*111ee~e~r~a~ft~ar-JilV~i4*~e""""'E~~.a~i~~***&fiR~:~~-MMaa~kRR~&*afinaafiR*a*a-MiK*aMR*&*!*a,.;.5 ltemeer arid Vtee Shairman, Operaetfilf' Manager 6relittl e!' his eesigRea, Ii' (* h 0

" I

• I J

-*r-U Jr9 OCIDPJ(ISI Ii'.~ **,,,

ALIEBNAIES 6 Is I l. 3 All aleer'ftaee memeeu shall ee appeirteee i:ft wrieirtg ey ehe SORG C'Aa i. RI aa,

a.

Vi:ee Cffaia*R &Rall las me11ber1 gf StatloA maaasement e,

Me mere eh:aft we aleernaees te meeen shall pareiei:pate a:!

oee:,,,~

IH*iiH'I i.R iQRC,ai;;t;i"i'Sh& a: aA;* QA* me*ti A(§ tla* ir ra spec r i ire liepal'S.IR;,

e.

t.lee!'ltal98 fel' lllCllBCl'S wiil 'f\\85 11ake.., pasc af 'aRa ua'Si.f\\g

~W:Eli""*"°'

• rb*n the members rhe alternare repr*s*nrs is also present.

MEETING fREOUENCY 6,5.l.4 The SORC shall meec at least once per calendar mont:h and as conv.:r,.:.=.

by che SORC Chairman or his designated alternat:e.

QUORUM 6,5,l.5 The minimum quorum of che SORC necessary for the performance of ::.e SORC responsibility and authority provisions of these technical specif~ca:~o~s shall consist of the Chairman or his designated alternate and five memoers including alt:ernates.

SE'S rwsEQ I Tr:> G.S'. /.~

SALEM - UNIT l 6-/'/

Amendment No, 62

INSERT TO SECTION 6.5.1.2 Chairman:

Member and Vice Chairman:

Member and Vice Chairman:

Member and Vice Chairman:

Member:

Member:

Member:

Member:

Member:

. Member:

Member:

General Manager -

Salem Operations Maintenance Manager Operations Manager Technical Manager Radiation Protection/Chemistry Manager Radiation Protection Engineer Chemistry Engineer Maintenance Engineers Operating Engineers Technical Engineers (Group Heads)

Onsite Safety Review Engineer INSERT TO SECTION 6.5.1.3 ALTERNATES 6.5.1.3 Alternates:

a.

Alternates shall be appointed by the SORC Chairman in writing.

b.

Only designated Vice chairmen may act as Chairman of a SORC meeting in the absence of the General Manager -

Salem Operations.

c.

Alternates shall only represent their respective departments.

d.

The Senior Nuclear Shift Supervisor (SNSS) may act as an alternate for the Operations Manager or an Operating Engineer.

The SNSS may also act as an alternate when the Operations Manager is acting as Chairman.

INSERT TO SECTION 6.5.1.5

a.

No more than two members or one member and one alternate from any individual department will make up part of the voting quorum.

b.

If the Chairman for a meeting is a Vice Chairman, then up to two additional members from the same department (or one member and one alternate) may be part of the voting quorum.

6.5.1.6 The Station Ooerations ~eview :ommi::ee sna:

e ~es::-s*:*e --~

a.

~; r11

a. 1ocFR.!f0.5q e11a/w:d,-,,,.,

Review of: (1) Station Administrative Crocedures ana :Rar;es :-e~e-and (2) Newly created orocedures or cnanges to exis:~rg :roce:~~es that inv;lve i i 1gnificant safety is!~e as described in Sec:~:~

6.5.3.2.d.

c.~,,~~s -Merefo

+Ii~ I Je~" ire c:o..

10CF~ ¢.S"'j Sa.Pe ev~!""-4 f;o,,,

b.

Review of all proposed tests and experiments that affect nuc~ear safety.

c.

Review of all proposed changes to Appendix "A" Technical Specifications.

d.

Review of all prooosed changes or modifications to olant sys:ems

~~

eauipment that affect nuclear safety.

e.

Review of the safety evaluations that have been completed unae~ :~e provisions of 10 CFR 50.59.

f.

Investigation of all violations of the Technical Specifications including the ~Fe~aFati;n ana faFwaPaing af reports covering evaluation and reconrnendations to prevent recurrence te t~e ~ice PPesiaent ana C~e.f. NwcleaF QffiGeF ana tRe GeneFal ManageP -

Nt1eleaP Safety Review.

g.

Review of all REPORTABLE EVENTS.

h.

Review of facility operations to detect potential nuclear safe!J hazards.

i.

Performance of special reviews, investigations or analyses ana reports tnereon as reauested by the General Manager - Salem Operations. eP Gu1enl

~al'la;el" N1:1e l HI" Safety Ro+ew-:-

j.

Review of the Facility Security Plan and implementing procedures a~:

k..

procedures

m.

Review of all unplanned on-site releases of *1dioactivity to :ne environs including the preparation of reports coverlng evaiuaticl"I.

recorrmendations and disposition of the corrective action to oreve~:

I' l"I I

recurrence ana tRe farwardi Ag af tRHC FUGl"t3 te tJ!le 1v~e rcr=es * :ec:

• 1111& Cl!lief Nwcleap~ffi'ff, ana"'"'FI* C:111cr~ ~~"

= N1:1chaP Sa.f~

Review.

SALEM - UNIT l 6-8 Amendment No. 99

~ESPONSI3[L!TIES (continued)

n.

Review of changes to the PROCESS CONTROL MANUAL ana

~e ~==-s:-~

DOSE CALCULATION MANUAL.

SORC REVIEW PROCESS 6.5.1.7 A technical review and control system utilizing qualified reviewe~s shall function to perform the periodic or routine review of procedures anc changes thereto. Details of this technical review process are proviaea in Section 6.5.3.

AUTHORITY 6.5.1.8 The Station Operations Revi?.w Committee shall:

I r:---;----r--------

I, ; ndi'c.4finq Pro~;ole

a.

Reeemffie~e to the General Manager - Salem Operationsfwritten aoo~~1a'.

rec.ot'l'ltr'let1daf;ot1s or disapproval of items considered under 6.5.1.6 (a) tl:iPe1:119t:i (e)

b.

above.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President and Chief Nuclear Officer and the General Manager - Nuclear Safety Re 11 iiw of disagreement between the SORC and the General Manager -

Salem Operations; however, the General Manager - Salem Operations shall have responsibility for resolution of such disagreements '

pursuant to 6.1.1 above.

RECORos~<--....... 1 ANO REPORTS I 6.5.1.9 The Station Operations Review Committee shall maintain written minutes of each meeting and copies shall be providea to the Vice Pres'den: a~~

Chief Nuclear Officer, the General Manager -1Nuclear Safety Re*o*iew and tne

~anager -,..OH Site Revie-

IQ /..1 A

'I

]

_ ~ iry

~~c-cnu1f!.e ctr1()(.

6.5.2 NUCLEAR SAFETY REVIEW FUNCTION 6.5.2.1 The Nuclear Safety Re1;*ieH Department fN-5-R+ shall function to provide the independent safety review program and audit of designated activities.

COP4POS I TI ON

§.§.2.Z NSR sf:lall eeAsist ef tAe GeAeral MaAager

~1::1eleaP Safety ~evie11. :r:

MaRa§eF - QFl*Site Safety Revie*.., GP91:Ji3 (SRG).

11IAO is Sl:J!3!39Pteel ey at leas: ~a *..-

didicatad, fYll*time eRgiFleeFs leeatee or:i-site, aRe tf:le MaRa§eF Qff*Site Review GFOl:Jr;l (9SR) '11Ae is Sl:J!3!30f'teel ey at least fOl:JP eeeiieatee, f1::1ll-th1e enginee~s lgGated eff*site.* TAe GSR staff sRa11

~assess e*r;ierieAee aAe eam~eteAee iA. tRe ~eAeral areas listee iA SeetieA 6.5.2.4. TAe GeAeral

~aAa~:c

~nd Mar:iageFs shall eeteFmir:ie \\1Aen aei~itional teef:!Flieal ex13eFts SR01::1l~ assis~

ir:i Feviews of eom~lex 13Fo91ems.

• ~ir:ise the NijeleaF Qe13aFtmer:it is leeate~ or:i AFtifieial Islar:ie site, tAe terffis 11 eA site" al'le "eff site" eeAvey the eiistir:ietioR betweer:i ir:iside ar:id Gbltiide the statiQn hnci, rii~i,ti 11 ily SALEM - UN IT 1 6-9 Amendment No. 99

INSERT 1 TO SECTION 6.5.2 COMPOSITION 6.5.2.2 The Nuclear Safety Department, under the cognizance of the General Manager - Quality Assurance and Nuclear Safety, shall consist of the Manager - Nuclear Safety, the Offsite Safety Review staff (OSR) and the Onsite Safety Review Group (SRG).

The OSR staff and the SRG each consist of at least four dedicated, full-time engineers.

The Manager - Nuclear Safety and the Offsite Safety Review staff shall meet or exceed the qualifications described in Section 4.7 of ANS 3.1 -

1981 and shall be guided by the provisions for independent review described in Section 4.3 of ANSI NlS.7 -

1976 (ANS 3.2).

The Offsite Safety Review staff shall generally possess experience and competence in the areas listed in Section 6.5.2.4.l.

A system of qualified reviewers from other technical organizations may be used 'to augment OSR staff expertise in the disciplines of Section 6.5.2.4.l, where appropriate.

such qualified reviewers shall meet the same qualification requirements as the Offsite Safety Review Staff, and shall not have been involved with performance of the original work*

The Onsite Safety Review Group staff shall meet or exceed the qualifications described in Section 4.4 of ANS 3.l - 1981.

_*.*_*j..:

~-

~JSR shall 1:1t; 1iz9 a syste1+1 g; g61a'i;iee ce'J;e,,.*ecs *l"oFR o::iex: :::ec*:.:

organizations ta a61g~int i~$ exgec~ise :n tne disc:o~ ines af Sec:isc :.*. _.

~61Eh qualified reviewers sh al 1 ~eet :!ie saFAe eua ii fi ca ti eA

'e~::i; eme. ".!5 B

~JSR staff, aAd *,<ill nat ha11e geen inveived with ser*orR'1aAee of tAe SF'gisa

\\JOl"k.

The MaAa§el" Gff Site Ri 11 iew and Staff shall ~eet er eKeeed the q1:1alifications described in Section 4.7 of ANS 3.1(1981) aAe snall

~e g~:eee by the prov is i ans for independent re*;i e11 eleseri bed i l"I Secti 01~ 4. 3 of AlqS i

~IH3.7 (1979)

(G~IS J,2). The Mana§er *On Site Re*;iw aAel staff,.;1: ~eet a.

exceed the qblalificatiens describeEI iA.Seetion 4.4 ef APJS 3.1 (1981).

~y Hue N1o<e lea.r t;.._fidy Oeparfmel'1f CONSULTANTS or o+lier +eckfllc.a( e.,,:perfs fie e.><kr'l'f nec.~S"ary 6.5.2.3 Consultants shall be utilized~;-e~-ST-1'R+l:i-e-El-8-¥--~e-i.~~.a.-i-~~~..i::,_..~

Nuel ear Safety Revi e11 to provi ele e)(pel"t OFFiisrrE1REVIEWlGR8HP l<o~RJI

~sTo.FFj 6.5.2.4 The OH Site Re'o'ie*t1 Grebli:i /os~shall function to provide indepencen:

review and audit of designated activities in the areas of:

a. Nuclear Power Plant Operations

b. Nuclear Engineering

c. Chemistry and Radiochemistry

d. Meta 11 urgy

e. Instrumentation and Control

f. Radiological Safety

g. Mechanical Engineering

h. Electrical Engineering i. Quality Assurance

j. Nondestructive Testing

k. Emergency Preparedness Ti~e OSR sFlal 1 al se ful"leti el"I te e><ami Ae 191 al"lt apel"'ati R§ cl':laraeteri sti cs. 'iRC q ssuaRees, i l"leiustl"y ach*i soi i es, Li eel"lsee ['o'el"lt Re19el"'ts, al"la etFlel"' seuPees wl':lich ~ay iRdieate aFeas for i~~reviR§ ~laRt safety.

SALEM -

UN IT 1 6-9a Amendment No. 99

.:. : '*' : \\I : : -

~

~ ~ \\} : =:w

'J.

I

~+4 f'f I 6.5.2.4.~The OSR shall review:

"rlie

a.

af ety vEva 1 uat i ans for"'

l m

Q})

~hanges to procedures, equipment, or systems~and

@ vfests or experiments complet~d under the provisions of Seetie~

50.59 10 CFR to verify that such actions did not constit~te an unrev1 ewe safety questi"ontGJ

, arid ~fs o-r eJt'fer.*menls

b.

Proposed changes to procedur~s, equipment, or systems that invo~*;e an unrevi ewed safety question as defined in Seeti Ol"lf50. 59. 110 c:=~I.

e.

Pl"e19esee tests el" eit19ePiFReFlts tF!at iFivelve aFl uAPevie"ee safe:,*

~~estieFl as eefiFiee iFl g9etieFl 59.§9, 19GFR.

~~-

Proposed changes :o Technical Specifications or to the Operating Li censej J~.

Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; e/.

Significant operating abnormalities or deviations from normal arrd expected performance of plant equipment that affect nuclear safety; All REPORTABLE EVENTSj All recognized indications of an ~nanticipated deficiency in some aspect of design or operation of safety*l"elate~ structures, systems A.I-c..s,,.,fo( 4~+

or component.;

llUC /eo.r 5q,.f.efy i-------------

AUDITS 3

6.5.2.4.t under the

+4e 0& R. S -/q,.fF.

1'1e, e 4u.cl;f5 Sha/{ el/GM'/f'~:

a.

b.

c.

Reports and meeting minutes of the Station Operations Review Cammi tteej Audits of cognizance fe~~ifea te be performed The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

The performance, training, and qualifications of the entire fac~ii:y staff at least once per 12 months.

The results of actions taken to correct deficiencies occurr* -~ in facility equipment, structures, systems, or method of operat ;n trat affect nuclear safety at least once per 6 months.

d.

The performance of activities required by Assurance Program to meet the Criteria of least once per 24 months.

~e Opera~~al Quality Appendix B (11)0CFR50, at to SALEM

• UN IT 1 6*10 Amendment No. 99 I

• -*4*1*.. --.--

e.

The Fac11ity Emergency ~lan and imo1ementing oroceaures ~: eas:

once per 12.months.

f.

The Facility Security Plan and implementing procedures at ~east J,...

• ~ -

per 12 months.

/

Gw:a.f,* fy-Assu,-anee 0</ICA

g.

Any other area of facility operation considered aooropriate by the General Manager - Nuclear Safety -R-9 1dew or the Vice President and

h.

i.

Chief Nuclear Officer.

The Facility Fire Protectio~ Program and implementing procedures at least once per 24 months.

~

The if'(l(Jle~r?l'/n nen

'°'"'

iF1ele13eF1eleF1~ire protection and loss prevention program iRs~eEtieR aF1el ablelit SAall ee 13erfo1med at least once per 12 rnont~s

~~utilizing eith~~~ified of~site licensee or an outs'ce

~f1 re protection

'""'r pro'feef:o~ en.:;.,flt!erS tA.

Ct!>A$~/f411f

_.,._,_~ ______

v __

..l An iF1s13ectieF1 aRel ablelit ef the fiFe 13PeteetieA aFlel less 13Pe~eF1tieF1 J3P9gPaff! Sfla11Be13ePf6Pffleel By a ~l:lalified OUtSidetfire'tc.onsultant

• S~I/ la~ i-----;"""1 east once per 36 months.

j;nJe~tJe11fl '-iProfeefii>n j uti/;1:eJ 4f jK.

The radiological environmental monitoring program and the results thereo~a 1 east once pe_r 12 months.

(t'l4.

The above audits ~

be conducted by the Nblel eu Qua 1 i ty Assurance Department or an independent consultant.as Pe~~iFeel. Audit:.f..'Fo@o!;;,r.i~r-a"*'-

reesAnlleFleati er:1s sha 11 be reviewed byt &5-R-: l"'"e 0,,__,

p/411s at1d FiN<f "r,.,~E'1" ~

. S.,.AF~.

el, f reporfs ON-SITE SAFETY REVIEW GROUP( I

(?tG) I

.....~_c.t_i __

n *'

(

~-----------1 6.5.2.Sii'The OnBSite Safety Review Group (SRG) shall function to provide: tne fUrU.TIO/I/

review of plant design and operating exp*erience for potential opportunities :o improve plant safety; the evaluation* of plant operations and maintenance activities; and advice to management on the overall quality and safety of plant operations.

The SRG shall make recommendations for revised procedures, equipment modifications, or other means of improving plant safety to appropriate

. station/ corporate management.

RESPONSIBILITIES

1.

6.5.2.5.X The SRG shall be responsible for:

a.

Review of selected plant operating characteristics, NRC issuances.

industry advisories, and other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety.

b.

Review of selected facility features, equipment, and systems.

SALEM -

UN IT 1.

6-11 Amendment No.99

INSERT 2 TO SECTION 6.5.2 RECORDS ANQ REPORTS 6.5.2.4.4 Records of OSR activities shall be maintained.

Reports of reviews and audits shall be prepared and distributed as indicated below:

a.

The results of reviews performed pursuant to Section 6.5.2.4.2 shall be reported to the Vice President and Chief Nuclear Officer at least monthly.

b.

Audit reports prepared pursuant to Section 6.5.2.4.3 shall be forwarded by the auditing organization to the Vice President and Chief Nuclear Officer and to the management positions responsible for the areas audited (l) within 30 days after completion ot the audit for those audits conducted by the Quality Assurance Department, and (2) within 60 days after completion of the audit for those audits conducted by an independent consultant.

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (continued)

c.

Review of selected procedures and plant activities includinq maintenance, modification, operational problems, and operational analysis.

d.

Surveillance of selected plant operations and maintenance activities to provide independent verification* that they are performed correctly and that human errors are reduced to as low as reasonably achievable.

NA-AUTHORITY 6.5.2.6 N&R-hail report* to and advise the Vice President and Chief Nuclear Officer on those areas of responsibility specified in Sections 6.5.2.4 and 6.5.2.5.

6.S.2.7 Reeeras ef NSR aetivities saall se preparea aad maiataiaea. Re~erts et reviews aad aadits shall se distriaated as fellews:

a.

Reperts et reviews incompa1sed ~Y SectioD 6 S 2 4.1 i~eve, shall se prepared, appreved aad ferwaraea te the Viee Presideat aft~ C~ief Naelear Gffieer, witaia 14 Qay1 fgllgwiag cempletign ;f tAi ri;*iew.

a.

A~dit reperts eaeempassed sy Seetiea 6.S.2.4.2 ahe?e, s~all he f erwarded te the Vise Presiaeat aa4 Chief Nuelear Gf f ieer aee te tae managemeet pesitiens respeasible fer the areas a~aitea wi;eia JG days after eempletiea et the audit.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Proqrams required by Technical Specification 6.8 and other procedures which affect nuclear safety as determined by the General Manaqer - Salem Operations, other than editorial or typoqraphical chanqes shall be reviewed as follows:

PROCEDURE'RELATED DOCUMENTS 6.5.3.2 Procedures, Proqram and chanqes thereto shall be reviewed as follows:

a.

Each newly created procedure, proqram or change thereto shall be independently reviewed by an individual knowledgeable in the subject area other than the individual who prepared the procedure, program or procedure change, but who may be from the same organization as the individual/group which prepared the procedure o~ procedure change. Procedures other than Station Administrative procedures will be approved by the appropriate Station Department Manager or by the Assistant General Manager - Salem Operations. Each Station Department Manager shall be responsible for a predesignated class ~f procedures. The General Manaqer - Salem Operations shall approv~

Station Administrative Procedures, Security Plan implementinq procedures and Emergency Plan implementing procedures.

• Not responsible for sign-off function SALEM - UNIT 1 6-12 Amendment No. 99

re~u;re a...

/OC FR 50.s-1

b.

On-the-soot changes to orocedures whicn clearly ao not :~a~;e --~

intent of the approved proceaures shall be aoorovea oy two

~e~oers of the plant management staff, at least one of whom

~olds a Se~;J~

Reac;tor Operator License. Revisions to procedures whicn may

~n 11oi ;e a change in intent of the approved procedures, shall be reviewea *n accordance with Section 6.5.3.2.a above.

c.

Individuals responsible for reviews performed in accordance with item 6.5.3.2a above shall be approved by the SORC Chairman and designated as Station Qualified Reviewers. A system of Station Qualified Reviewers, each of whom shall possess qualifications that meet or exceed the requirements of Section 4.4 of ANSI Nl8.l -

197~.

shall be maintained by the SORC Chairman. Each review shall include a written determination of whether or not additional cross-disciplinary review is necessary. If deemed necessary, sue~

review shall be performed by the appropriate designated review personnel.

-tk ose s~ff

d.

Manager determines that the documents involved Set.

e rM li<<tfio 11 1--~..-.. -a-~it-HT-!~i'A'"+-++~fHO-~IH-l:~'"t'"I'*~~. the documents shall be forwarded for SORC review and also to *6-R-for an independent review to determine whether or not an unreviewed safety question is involved, Pursuant to 10CFR50.59, NRC approval of items involving unrevie~ed safety questions or Technical Specification changes shall be obtained pri6r to implementation.

NON-PROCEDURE RELATED DOCUMENTS 6.5.3.3 Tests or experiments, changes to Technical Specifications, and changes to equipment or systems shall be forwarded for SORC review and also to

• 5-R-for an independent review to determine whether or not an unreviewed safety ques ion is 1nvo ve.

e resu ts o reviews will be provided to SORC.

Recommendations for approval are made by SORC to the General Manager - Salem Operations. Pursuant to 10CFR50.59, NRC approval of items involving unreviewed safety questions or requiring Technical Specification changes shall be obtained prior to implementation.

RECORosMA"'O gEPo~rs j 6.5.3.4 Written rec~~ds of reviews performed in accordance with it~6.5.3.2a above, including recommendations for approval or disapproval, shall be maintai.ned. Copies shall be provided to the General Manager - Salem Operations, SORC, *SR-and/or NRC as necessary when their reviews are requirea.

SALEM - UNIT 1

• 6-12a Amendment No. 99

.=. : :\\4 : '4 :

~ -

J ~ = = 'j -

6.6 RE~QRTABLE EVENT ACT:CN 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and/or a reoort suomitted purs~ar:

to the requirements of Section 50.73 to 10CFR Part 50, and

b.

Each REPORTABLE EVENT shall be reviewed by the SORC and the resultant Licensee Event Report submitted to and the Vice President and Chief Nuclear Officer.

6.7 SAFETY LIMIT VIOLATION 6.7.1 (The following actions shall be taken in the event a Safety Limit

~s violated:

a.

The unit shall be placed in at least HOT STANDBY within one hour.

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President and Chief Nuclear Officer and General Manager - Nuclear Safety Revie\\1 shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

/

Qua/;'/-

A,s,.l'ltr'lce 4flOI

c.

-A Safety Limit Violation R~port shall be prepared. The report shall be reviewed by the SORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Commission, the General Manager -

uclear Sa*ety Rev1ew and the Vice President and Chief Nuclear Offic r within 14 days of the violat1on.

Q.... ~kly A6$i.Cro.rice a~

SALEM - UN IT 1

. 6-12b Amendment No. 99

AOMINIST~ATIVE CONTROLS 6.8 PROCEDURES ANO

~OGRAMS 6.8.l Wr-itten pratl_dur"es shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recortm!nded in Appendix "A" of Regulatory Guide l.JJ. Revision 2, February 1978.

b.

Refueling operattons.

c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire PT-otection Program implementation.

g. _ PROCESS CONTROL PROGRAM imi>l ementat ion.

h.

OFFSITE DOSE CALCULATION AANUAL i""21ementation.

f.

~ality Assurance Progrant for effluent and environmental rTOnitoring.

6.a.z Each procedure and administrative policy of 6.8.l abav~. and changes 1

thereto, shall be reviewed and app*roved i.n acc:ardance with Specification 6.5.1.6 or 6.S.J. as appropriate, prior ta implem1ntation and reviewed pe~iodically as set forth in administrative procedures.

6.8.3 On-the-spot changes ta procedures of 6.8.l above may b9 made provided:

a.

The intent' of the original procedure is rot altered.

b.

The chang9 is approved by two l"l!mbers of the plant management staff, at least one of wham holds a Senior Reactor Operator's License on the unit affected.

c.

The change is c.bcu1n1nted and recetves the sant level o.f review and approval. as the original procedure under Specification 6.S.3.2a witnin 14 days of implementation.

SALEM - UN IT l 6-13 Amendment*Na. 62

ADMINISTRATIVE CQNTROLS 6.8.4 The folla...a:og programs shall be maintained:

a.

Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could. cont~in highly radioactive fluids during a serious transient ~r accident.to as low as practical levels. The systems include (recirculation spray, safety injection, chemical and volume control, gas stripper, recomb1ners, *** ). The program shall include the following:

(1) Preventative maintenance and periodic visual inspQction require-ments, and (ii) Integrated i eak test requirements for each system at refueling cycle intervals or less.

be In-Plant Radiation Monitoring A program which will ensure the capability to accurately detennine

. the airborne iodine concentration in areas under accident conditions.

This program shall include the following:

(i) Training of personnel, tii) Procedures for monitoring, and (1i1) Provisions for maintenance of sampling and analyses equipment.

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam gener~tor tube degradation. Tiiis program shall include:

(i)

Identification of a sampling schedule for the critical variables and the control points for these variables, (ii) Identification of the procedures used to measure the values of the critical variables, (iii) Identification of process sampling points, including monitoring at the discharge of the condensate pumps for evidence of condenser in-leakage.

(iv)

Procedures for the recording and management of data, I

(v)

Procedures defining corrective actions for off-control-point chemistry conditions, (vi)

A procedure identifying (a) the authority responsible fort.he interpretation of the data, and (b) the sequence and timing* of administrative events required to initiate corrective action.

SALEM - UNIT l 6-14 Amendment No. 59

ADMINISTRATIVE CONTROLS

q.

Backup Method for Determining Subcooling Margin A program which will ensure the capability to accurately

• monitor the Reactor Coolant System Subcool i ng Margin.

This program shall include the following:

(i)

Trafnfng of personnel, and (ff) Procedures for *monitoring

e. Postaccfdent Sampling A program* which will ensure the capability to obtain and analyze reactor coolant, radf oactive iod1 nes and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

(i)

Training of personnel (ii)

Procedures for saq>ling and analysis, (ff i) Provis tons for ma 1.ntenance of saq> 1 i ng and analysis equipment.

• It is acceptable ff the licensee maintains details of the program 1 n p_l ant ope rat f on manual$.

SALEM - UNIT 1 6-14a.

Amendment No. 67

ADMINISIRATIVE CONTROLS 6;9 REPORTlNG REQUIREMENTS ROUIINE REPORTS Aili RSfE!RIMLE 966URREHGES 6.9.l In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the

~Adminiscracor~o~Qffie* of l**P***i**..,. i*f******** unless otherwise noteQ, ~~"

1:-)

cJ.~. Nu.r:./eq,r Qef"/a.fort c._,_,:ssio,,, iJo,.,,,,,l",,f SIMIUP REPORT CD-rf-ro(

0~,.;,

Ust,,*n~fon, {J.C.

~55S,..,,;fl a-.

co f-o H..e 1--~~-L-.l-~....;;..._..;_;_~~~~~~~~~~~~~_.

• 6.9.1.l A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment co the license involving a planned increase in power level, (3) installation of fuel that has different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. AnY.

corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.l.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test-program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS fj)"

6.9.l.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March l of each year. ~e iBieial *ep*** shall ee s~eaie*ea p*i** ee Ma*eh l ef *he year 4 felle~iftg iRieial e*iG!eali.,.~

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

SALEM

• UNIT l Amendment No 67

AOMINISTRAT!VE CCNTROLS 6.9.l.S Reports ~equired on an annual basis shall include:

a.

+hermo {i.,ni nes-=~11+

Jos,' m efe r A tabula~io~on an annual basts of the number of station, utility and other personnel (tn~luding contractors) receiving exposures greacer than lOO mrem/yr and tht1~_assoctated man rem exposure according to wori< and job functions,~.g., reactor operations and surveillance, tnservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.

The dose assignment t~ various duty functions may be estimates based on pocket m

r f11R1 Daege measurements.

• Sma 11 exposures tota 11 t ng less than 2Cli of the individual total dose need not be accounted for.

In the aggregate, at least 801 of th& total whole body dose received fran external sources shall be assigned to spec1f1c major wo~

functions.

b.

Th*-c;cmpltte results of steam generator tube inservice inspections per.formed durt ng the report pert od (reference Specifi cat1 on 4.4.5.5.b).

MONTHLY OPERATING REPORT 6.9.l.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a rnonthl basis to the 91~eete~. Off1ee ef Mana~ement Informa-

u.

• uc ear egu atory omm ss on, Washington, o.c.

20555, with a copy

, no later than the 15th of each month following the calendar month covered by the report.

REPORTABLE OCCURRENCES

-f-o ~ USN'1.C. ffr1,.,111rsfr4 for, £ i'~,, I 6.9.l.7 Tl'le REPORTABLE OCCURRENCES ef S!'eeif1eatieAs S,9,la8 iAQ i.9,1.9 eel;w, inclijding c;rr1c;1¥* iCt1QAI iAd AllilWFIS ;; prev*At Fe,wFPeAGO, 5Aall Be-Fepertee ta tAe NRG.

SwpplemeAtal FepeFts ~*Y ;e requ1F9G ;; fijlly_Q1ser1;1 final reselijt1en ef eee~rrenea.

IA ease ef earre~;ed or swppl1111At11 rapor=ta, i lic1n111 1v1nt repo~ 1n111 ;,,;~lated aRd FefereAee sn1ll ;a ~iGI te ;Ra

r1gir

iil report d1t1.

PROMPT ~lOTIF!CATION WITH WRITIEN FOLLOWl:lP 1,9,1.a '"'* ~pes ef eveAts listed Delaw sAall De PepeFted witAil'I 24 ReuFs ey telepAGAI UIO CQAf1nned b¥ Ul19raptl 1 maiJgram, or ficsiiiilt tru:ismiSSiQn ta UHi Adftlil'listrater ef t~e Regional Office, er his designate nc later than the first woi=Xir:ig d1y fol1awiF19 tAe evel'lt, witA a wrietel'I fellewti'9 Pel'er'! witA1" H aays.

TI:la wirtteR fellewup re"ert sfta11 il'lelYde, as a ~1Ai~YM, a eempletee eapy af a 1 ieensee e"ent repo~ ferm.

rnfermatien pro~ided o" the 1 ieensee event repert fof"'AI sRill ee supple~eAted, as Reeded, ey ada1tieRal Rarrat1ve material te previee eem"lete ex"lanaeiel'I ef t~e eireijmstal'lees !ijrreijnding tfte eve,.ta Y:tli1s cabulation supplements the requirements of section 20.407 of 10 CFR Part 20.

SALEM - UNIT l 6-16 Amendment No. ~

INSERT TO SECTION 6.9.1.5

c.

The results of any specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.8.

The following information sh&ll be included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while the limit was excfteded and results of one analysis after the radioiodine activity was reduced to less th.an the limit.

E&ch result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodin* isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above th* steady state level; and (S) Th* time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

ai1"Jre~. the reactor protection system or ot

-:er sys:e:.is s... :i;;c-:

limiting safety system settings to initiate tne required ~ri:itec::1~

functton by the time a monitored par~meter r!acnes th~ set:oint s: c~

fied as the limiting safety systam setting in the technical s:iec;. ~:l tions or failure to complete the required ?rote~tive function.

b.

Op ration of the unit or affected systems when any parameter or ocera-tio subject to a limiting condition for operatic~ is less conserva-tive han the least conservative aspect of the limiting nditicn ~or operat on established 1n the technical specifications.

c.

Abnormal gradation discovered in fuel cladding, re coolant pressure b ndary, or primary containment.

d.

Reactivity an alies involving disagreement wit the predicted *1abe of reactivity b lance under steady state condi ions during power operation greate than or equal to l: delta 7k; a calculated reac-tivity balance in eating a SHUTOOWN MARGI. less conservati*1e t:ian specifi~ in the te nical specif1cat1ons short-term reactivity _

increases that corres and to a reactor riod of less than 5 seconds or, if subcritical, an nplanned react vity insertion of mare than O.SS delta k/k; or occur enc:e of any nplanne<i criticality.

e.

re components whi cl'I prevents or

f.

g.

ii.

. i.

j

• could prevent, by itself, tl'I f

f111ment of the functional,require-

~ents of system(s) used ~o cop with accidents analyzed in the SAR.

Conditions arising fr.

natural or man result of the event require unit shutdow operation of safety systems, or other rotective measures req 'red by technical speci f'i cations.

in the transient or analyses or in :he methods use for such analyses as described in e safety analysis repor"t or *n the bases for the technical specific tions that nave *:Jr could ha

?ermitted reactor operation in a manner ess conser*1ati'le than a Wiied 1 n the analyses. *

?erf. rmance of stnictures, ~ystems, or r ecial action or corrective measures to prevent operati n in a nner less conservative than assumed in the accident anal ses in

~~e safety analysis reoort or technical specifications bases; o discover:

during unit life of conditions not specifically considered in t~e safety analysis repor~ or technical specifications tnat re~uir_

remedial action or correcti'le measures to ?revent the existence development of an unsafe cond.ltion.

Offsite releases of' radioactive materials in liquid fnd ;as~9us ~f~~u ents that exceed the limits of' Specification 3.n.t.i. or 3..... 2. ***

S.3.L~~ -

!J~!i l 6-t 7*

i3.mendment 'lo.

s~

~OMINIST~ATIVE CONTROLS

~

Exceeding the limits tn Specification 3.lt.1.4 or 3.11.2.6 for the storage of radioactive materials in the listad tanks. ihe written follow-up report shall include a schedule and a description of ti*~i~ies ~l~nned and/or taken to reduce the contents to *11ithi~~

sp c1 fied 11m1ts.* L--------*-,.. -.....---...--..---- --.----:--.---.-..-----

• ~ v * ;

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• _

/

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-~*-L'

• ':/'"'a..-:ri

~,~,......:*r.;-.,

i...x:c.. *.**,'*

G-.-ft_~ (.__r_

TH!RTY DAY 'llRITT~~ REPORTS W~d.. -.~L-'.

1~*~

c::**~..:.::.:<,~.,~ *" 0".'f/ h ~ rk.J".""'.{

• ,/

~~

---..._..._..____......,/

6.9.l.9 The ty, es o events listed below shall be the subject

~written reports to th dmini rater of the Regional Office within th ty days of occurrence of t e event The written report ~hall include, s a minimum, a completed copy of a lice ee event report form.

Informati n provided on the licensee event report form shall be supplemented, as nee d, by additional narrative material to provi complete explanation of e circumstances surrounding the event.

a.

Reactor ~rotection or engineered afety feature instrument settings which are found to be less co servative than those estab-1 i shed by the technical sp cificatio but which do not prevent the fulfillment of the function requ ements of affected systems.

b.

Conditions leading to operatic n a degraded mode permitted by a limiting condition for operat* n r plant shutdown required by a limiting condition for aper ion.

c.

Observed inadequacies in he implemen ation of administrative or procedural controls whi h threaten to use reduction of degree of redundancy provided i reactor protectio systems or engineered safety feature systems.

d.

Abnormal degrada ion of systems other than th se specified in 6.9.1.8.c abov designed to contain radioactiv_ material resulting from t~e fis on process.

e.

An unplan d offsite releases of l) more than ~cur radioacthe

.materia in liquid effluents, 2) more than 150 curies of noble gas in gaseo effluents. The report of an unplanne~ offsite elease of radi active material shall include the follow* ig informa ion *

• A description of the event and equipment ~~valved.

Cause(s) for the unplanned release.

3. Actions taken to prevent recurrence.

4. Consequences of the unplanned ~elease.

SALEM - UNIT l 6-18 Amendment No. 59

UNIT 2 MARKUP PAGES

nmg DWlflTIOtfS s1rno1 1.0 ppnunou DlnNED TDMS ******.***

ACTIOR ** ! **************

AXIAL FLUX DIFF!UNC!

CHANNEL CALIBRATION CHANNEL CHECK ******

CHANNEL FUNCTIONAL TEST CONTAINMENT INTEGRITY COtmlOLLED L!AKAGI CORI ALTlllATION DOS!.. EQUlVAL!N'r 1*131...*.

E*AVERAGE DISINTEGRATION ENERGY ENGIN!EUD SAFETY FEA'l'UU RESPONSE TIME FREQUENCY NOTATION FULLY WITHDRAWN *...

GAs!OtJS RADVAST! TREATMENT SYST!X IDENTIFIED L!AlCA~! ******

MEM!ER(S) OF THI PUILIC OrFslTI DOSE CALCULATION MANUAL (ODCK)

OPERABLE

• OPERABIµTY OPERATIONAL MODE.....

PK!SlCS TESTS PRESSUU BOUNDARY L!AICAG!

PROCESS CONTROL PROGRAM (PCP)

PURGE-PURGING..*..*.......

QUADRAN'l' POW!ll TILT RATIO RATED THERMAL POWEil ******

REACTOR TRIP SYSTEM RESPONSE TIMI REPORTABLE'9GCUIRENe!

SHUTDOWN MAR.GIN SIT! BOUNDARY..

SOLIDIFICATION -

4

~

• SOURCE CHECK STAGGERED TiST BASIS TllERMAL POWD ********

UNIDElftIFIED Lr.AlCAGI UNllS'l'RICTED AREA...

Vllft'lLATION EXHAUST TllEA'IMENT SYSTEM VElftDfG 8

8 e e e 8 e e 8

8 8

e I

I I

I I

I I

I I

I I

I I

I I

I I

SALEK

• UNIT 2 I

IAGI.

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.. 1-1

.* 1-1

.1-1

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... 1-4

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.1-5

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... 1-6

... 1-6

.. 1-6 I.1*6

... 1-7

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... 1-7

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.. **1"-

AmendMnc No. 7 8 \\

ADMINISTRATIVE CONTROLS

=============================================================

SECTION 6.1 RESPONSIBILITY............

6.2 ORGANIZATION Onsite and Offsite Organizations Facility Staff.......

Shift Technical Advisor 6.J FACILITY STAFF QUALIFICATION I

I I

'I I

PAGE.

6-1 6-1 6-1 6-% 7 6-$ 7 6.4 TRAINING 6-17 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW CO!!\\HITTEE Function Composition...

Alternates Meetinq F~equency Quorum.....

Responsibilities I so RC. 1-I --->.:!t Review Process Authority....

Is o.flol '2epod.s I Record:;a;.......

6.5.2 NUCLEAR SAFETY REVIEW Function I

Composition.....

I (os~)

Consul tan ts......

.----~ff~ ite Review Grettp-V.

eview udits.*........ _* *~

..---;,.;nt(Site Safety Review Group~

esponsibilities Authority R.ec..ords.

SALEM - UNIT 2 XVIII

~

6-if 8 6-iffl 6-iYe 6-(9 6-3'6 6-,8 tt 6-.H 10 6-810 6-H 10 6-~10 6-J310 6-.,9-a II 6-~11 6-}61~

6-l,..0"1;;;>

6-lt! t3 6-.M"1r 6-)Z 1'{

~-13

(;'-13

'(;~ti Amendment No. 76

ADMINISTRATIVE CONTROLS

s====================================================================

SECTION 6.5.3 TECHNICAL REVIEW AND CONTROL..

6.6 RIPORTABLE EVENT ACTION.

6.7 SAFETY LIMIT VIOLATION 6.8 PROCEDURES AND PROGRAMS.

6.9 REPORTING REQUIREMENTS 6.9.-1 ROUTINE REPORTS 6.9.2 SPECIAL REPORTS 6.10 RECORD RETENTION..

6.ll RADIATION PROTECTION PROGRAM 6.12 HIGH RADIATION AREA..

6.13 PROCESS CONTROL PROGRAM *.

6.14 OFFSITE DOSE CALCULATION MANUAL 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS.. *...

SALEM - UNIT 2 XIX 6-lZi ltJ 6-)t!'" It/

6-p( ;l3

• 6-~:;23

• 6-~-;25'

. 6-21'~.f'

. 6-it' ?C

• 6-U'-:2 7 Amendment No.75

DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE OCCURR:ENCE ~

t V'C. Nl' 1.27 A REPORTABLE OCGURR:FiNCE shall be S~eeifies6i©A8 9:9:1:8 ana 6.9.1.9.

SHUTDOWN MARGIN any of those conditions specified in

~cft'o11 5"0.73 +o 10 c.FR Pa,rf 50 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be FULLY WITHDRAWN.

SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3, and which defines the exclusion area as shown in Figure 5.1-1.

SOLIDIFICATION 1.30 SOLIDIFICATION shall be the conversion of wet radioactive wastes into a form that meets shipping and burial ground requirements.

SOURCE CHECK 1.31 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of:

(n)

a.

A test schedule forJ;r"""systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into)\\__equal subintervals,

_,.(_n J SALEM - UNIT 2 1-6 Amendment No. 66 I

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,. IY11Ul1nt

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11 wti1t111 ta 11att....,..,.,. '"" 11c11a 'q*

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d't_SV'ibvi1Gft., Md fncnlSH,,,

lS u &aount f'o.. IMftUfl~"' Ultnnca 1114 ~-- fftUHSM bf 51 to

&c:auft'C tor 1111*SUrtmlft1 unc.~itn'7*

SM.!M

• UNIT Z ll* z.7 Mlendment Na. el".

I~ST~U~ENTAT!ON RAOIOACTIVt LIOUIO EFFLUENT MONITORING INSTRUMENTATION LIMIT!NG COliOITIOH FOR OPERAT!ON 3.3.3.S The radioactive liquid effluent monitoring 1nstMJ111entation channels shown in Table 3.3-l2 shall be OPERABLE with thei~ alarm/trip setpoints set to ensure that the limits of Specification 3.ll.l.l are not exceeded. Tha alal"!ll/tr1p setpoints of these channels shall be determined in accordance with the OFrSITE COSE CALCULATION MANUAL (000!).*

APPLICABILITY: *At all times.

ACTtON:

a. With a radioactive liquid effluent mcnitoring instr"Umentation channel alann/trip s*tpaint less conservative than r~uired by the abave spec1f1catian, without delay suspend the ~lease of radioactive. lfquid effluents mcnitored by the affected channel or declare the channel inoperable or change the s*tpoint so it is acceptably conservative *

. b. Wfth less than the nrinirnum n-er of radioactive -liquid effluent mcnitoring fnstr"Umentation channels OPERABLE, take the ACTION sho~n fn Table 3.3-12. E.xert best efforts to ~tur:i the instrument to operable status ~ithin 30 days and, if unsu~cessful, explain in th* next semi-annual radioactive effluent ~lease ~part wny the 1noperability was not cor~ed in a timely manner.

c.

The provisions of S12ecHications 3.o.3J3.0.4t-~i5~9.l.9~a a~ not applicable.

SURVILLANCE REQUIREMENTS 4.3.3.S Each radioactive liquid *effluent rnan1tor1ng instMJ111entation channel shall be demanstrated OPERASLi by performance of the OIANNEl.. CMEC<,

SOURC~

OIECX, 04ANMEl.. CALIBRATION, and OIANNEI.. FUNCTIONAL ~ST operations at the frequ*nc1es sha.n in Table 4.3-12.

SALEM

• UNIT 2 3/4 3.53

.Amendment No. 28

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent !11lnitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

The alarm/trip setpoints

_;;f these channels shall be determined in accordance with the

~OOCM¢ APPLICABILITY:

As shown in Table 3.3-13 ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay *suspend the rel ease of radioactive gaseous

• effluents monitored by the affected. channel or declare the channel inoperable or change the setpoi nt so it is ac*ceptably conservative.

b.

With less than the mini111Jm number of. radioactive gaseous effluent monitoring instrumentation channels O~ERABLE, take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next semi-annual radioactive effluent release report why the inoperability was not corrected in ~timely manner.

c. The provisions of Specifications 3.0.3~3.0.4,~

9.9.l.9.a are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, AND CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

SALEM - UNIT 2 3/4 3-59 Amendment No. 53

REACTOR COOLAHT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

b.

4.4.6.5

a.

b.

9.

Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service establish a baseline condition of the tubing. This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.

Reports Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.

The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the period in which the inspection was completed.

This report shall include:

1.

Number and extent of tubes inspected.

2.

Location and percent of wall-thickness penetration for each indication of an imperfection.

3.

Identification of tubes plugged.

c.

Results of steam generator tube inspections which fall into Category C-3-aAa Pe~wiPe pPelRpt AetifieatieR ef tAe SeRIRlissieR SAall ee FepeFtea pl:iFswaAt te Speeifieati'eA S.9.l pPieP te PeSl:ilRptieR af plaAt apeFatieA.

T~e wFitteR fallawl:ip af t~is PepaFt,~hall provide a description of investigations conducted to determin1 cause of the tube degradation and corrective measures taken to pre1 ent recurrence.

S~a.f/ be ev~/r.t4f-e,j -For reporfci~;/,*1f P.u~U411f -fb

{0CFf2. o0.7~ o..rio/

{OCFR_ 6"0.73. T!.e evq/"<o.ho,,-,

5 ~o. (/ be olocul'11t?rdeo/,

~.r1.c/

SALEM - UNIT 2 3/4 4-i3

c:

z N

w I

U1 TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION 111 IAWLE INSPECTION 2ND SAMPLE INSPECTION lRD SAMPLE INSPECTION Sampae su.

R-..11 Action.Requif_.

Rault Ac1ion Requif_.

Rault Aclion Requited A minimum of C-1 None NIA NIA NIA NIA S Tubal*

S. G.

C-2 Plug deleclive 1ubn C-1 Nona NIA NIA and inspeel illddilioNI Plug dofeclive lubn C-1 None 2S tuba in 1hia S. G.

C-2 and inapecl illddilional C-2 Plug defeclive lubes 4S tuba in 1hi1 S. G.

PerfOJm.ction for C-J C-J raull ol fil11 IMlple P*form Klion lot C-J C-J rnJ11 of tir11 NIA NIA ump I*

C-J lnapect *II tuba in All other thi1 S. G.. plug do*

S. G.1 ere None NIA NIA lective lubea Md C-1 inlpCICt 2S tubn in Some S. G.1 P*lorm.ction tor NIA NIA OKia Olhur s. G.

C-2 but no C-2 rnult of MCOnd

~f.otilicetion

~iliomt umple S. G...re 10 NRC punumt C-J to 6:9:1-r Additionel lnapect iiill lubti in S. G. ia C-J ~

S. G. and plug delec*iv* tub91.

1oc.r;fi 50.('J a..J

..,.....Jwi1ilicetion NIA NIA 10 cFR..E>o.731 4.5 10 NRC purlUMt

<t.fp/:c..ttfole _

to ~

1:8: S

• J ~"" Whou1 N ii lhe number ol llOilm genorii11or1 in lho unit, *nd n ii 1he numbel ol 11um...,W*lotl inspect_.

n t.lu1 ing an in11>ec1ion

REACTOR COOLANT SYSTEM 3/4.4.9 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.9 The specific activity of the primary cdolant shall be limited to:

a.

Less than or equal to 1.0 µCi/gram DOSE EQUIVALENT I-131, and

b.

Less than or equal to 100/E µCi/gram.

APPLICABILITY:

MODES l, 2, 3, 4 and 5.

ACTION:

MODES 1, 2 and 3*:

a.

With the &petifis aetivity ef tRe pPimary eeelaAt gPeat-ef!--.t.Aa.n 1.Q J;1Ci/gram 99SE EQUIVALENT I-131 a1:1t witRiA tRe allewaale limit (belew and ta the left ef the liAe) shewn eA Fig1:1re 3.4*1, epePatieA may eeAtiA1:1e fer 1:1p t.e 48 het1rs pre~ided that.the e~mt1lati~e eperatiAg time 1:1AeeP tRese eire1:1mstaAees etees Aet e*eeeEI SQQ neurs iR aRy ceAsee1:1tive 12-meAtR perieet.

WitR tRe e1:1m1:1lative eperatiAg time at a primary eeelaAt speeifie aetivity greater tRaA er eei1:1al te

l. 0 µCi/gram DQSE EQUIVALENT I* 131 eMeeeEli A§ 5QQ heurs i A aRy eeAsee1:1tive 6-meAth periea, prepare and st1emit a Speeial Repert te the Ge111R1issien p1:1rs1:1ant te Speeifieatien 6.9.2 witRiA 3Q etays indicating the nt1mbef' ef hetlf'S aeeve this limit.

Tl:!e ~r9\\'i&i9AS Qf SpecificstieA 3~9.4 are net applieaale.

a..~.

With the specific activity of the primary coolant greater thaR..:st-

~

1.0 µCi/gram DOSE EQUIVALENT I-131 for more than 4a* hours during one L?_f continuous time interval or exceeding the limit line shown on Figur~ 3.4-1, be in at least HOT STANDBY with Tavg less th~00°F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

~

bf*

With the specific activity of the primary coolant greater thaR r:;i_...::71~0~ µCi/gram, be in at least HOT STANDBY with Tavg ~S00°F

~ w1th1n 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

..(.

• With Tavg ~Peater tRaA 9P eq~al te S00°F.

cfJ SALEM - UNIT 2 3/4 4*23

REACTOR CCOLAHT SYSTEM ACT!OH:

(Continu9d)

MODES 1, 2, 3, 4 Md S:

a.

With th* specific activity of the primary coolMt greater thM

1. 0 µC1/gyo* DOSE EQUIVAL!HT I*131 or greater thM 100/! µCi/gru, perlo~ th* s~11ng and analysis requil"eMnu of 1t* ~ of TIDl* 4.4*2 until the specific Aet1v1t coolMt f restored to w th1 n 1 ti 11 *1 u

1.

ftHcUp Sl8\\leP tli IHI')' IUAi "t 48 l'lei.P't SIPieP H tfte f 1 r-t'-

H.. 11 fft wtl1~ \\Re 11*1\\ di MSHiH,

2.

F.-1 ~....... ~..... NtilR,

a.

61........ fl IW llli 1Wfl)' *'W""1"' 48 llleuP-9,,1 IP "

\\M f1 pt' 1_,11 iR wtl1c.R ~ 11*1' -..1 llCIHIMG 1

4.

Hit'9Py 1f....,fl:lliRI 1.,1r1ti1n1, if lftY, stia,..1nt 48 l'l1wP1 StPilP W \\Re f1Ni 111111111 111 wflitll '"9 1 i*:f\\ -...1 MHllli; aM 5

• SURVEILLA14CE REQUIREMEHTS 4.4.9 Th* spec1f1c 1ct1Yi~ of th* pr1ury coolant shall b1 dlte~1"9d to b1

(

within tM 11*1tl by perlol"MnCa of th* SM1Pling and analysis progr* of T1Dl1 4.4*4

• SAUM* UNIT 2 3/4 4*24

CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION 3.6. 1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6. 1.6.

APPLICABILITY:

MODES *1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6. 1.6. 1 Containment Surfaces The structural integrity of the exposed accessible 1nter1or and exterior surfaces of the containment, includfng the liner plate, shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6. 1.2) by a visual inspection of these surfaces. This inspection shall be performed prior to the Type A contain-ment leakage rate test to verify no apparent changes in ~ppearance or other abnormal degradation.

4.6. 1.6.2 Reports Any abnormal degradation of the containment structure detected during the above required inspections shall be shall include a description of the condition of the concrete, the inspec ion procedure, the tolerances OQ cracking, and the corrective action taken.

SALEM - UNIT 2 3/4 6-8

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS.(Continued)

d.

At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting all diesel generators simultaneously, during shutdown, and verifying that all diesel generators accelerate to at least 900 rpm in less than or equal to 10 seconds.

4.8.1.1.3 The diesel fuel oil storage and transfer system shall be.demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying the level in each of the above required 20,000* gallon fuel storage tanks. *

2.

Verifying that both fuel transfer pumps can be started and transfer fue 1 from the 20, 000 ga 11 on storage tanks to the. day tanks.

b.

At least once per 92 days by verifying that a sample of diesel fuel from each of the.above required 20,000 gallon fuel storage tanks is within the acceptable limits specified in Table 1 of ASTM 0975-68 when checked for viscosity, water and sediment.

4.8.1.1.4 Reports. - All diesel generator failures, valid or non-valid, shall be reported to the Co1m1ission ursuant to Specification.

Reports of diesel generator failures sha 1 include the information re ommended in Regulatory Position C.3.b of Regulatory G ide 1.108, Revision 1, Augus 1977.

If the number of failures in the last 100 valid tests (on a per nu lear unit basis) is greater than or equal to 7, he report shall be suppleme ted to include the additional information recommen ed in Regulatory Position C 3.b of Regulatory Guide l.108, ~evision 1, August 977.

SALEM - UNIT 2 3/4 8-5

£. 9. ~ w:#.;,,

"30 da. s

~AO!OACTtVE EF~LUE~TS COSE -

~IMtTtNG COMOITtON ~OR OP~Ai!ON 3.11.1.2 Tite dasa or dost c:=-1 tmnt to a "'!HID 0' T"Ht PUii.IC fram rad1 a*c:tht

~ur1*1s 1n 1 tqu1d 1ff1uenc1 rwlHsed, fl"'Qll Hdl rucicir untt, to UHA!STKICT!D AAW (Sff '1gun 5.l*l) st111l be 1111'ftM:

a. Our1nt *"7 "llftur qy1~1r to 1111 tl'lu or ~1 ta 1.s ir-ea cn1 eou 1 body ud to l 1ss tl't1n or equi 1 ta S.,... ta Ut1 Of"11", ud

11.

Our1n9 Uf'1 ul1nUr 111r ta 1111 tl'tlft or equl ta l._ ta tl'I* totll bo* iftG ta 1111 tl'llft or equl to 10.-- to an, or91n.

AJP~ICAltltTY:

AC all t1.. s.

ACT?ON:

a.

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ot I> a 0

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II.

nte Dr'O'l111-onl of SJeC1 f1c:it1on 3.0.l IM l.0.4.,.. l'tOt ~OPl f Ubl **

• .11.1.2

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dlCll"ll1nl;d fn K:OtUftQ *1CJI tJI* ODQI IC lt1SC one* per ll ~, **

SAi.et

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"° ~,- llQl.IMOul "" '°.,,.,,,,....,, *...-~

no&n,* pd.I"'"" 6u'9Q na eis..,.., lllDHll * '° *iun11q *t

~uo,;-..o,u, 111.-uo.1 *

-..n1*i uan WCMSeai l'~ 1 *i*rt uo~'"'H>>dS ft annund *~ Dt u'"°" uo,ss..-~

• aa ;tmQfts Put 1.1tc1a.1e1,sw2i *** "'""',

• ar *it ssiaaH..... t.ri

'° sn:in u' '*'. ;amiin.Q aaoqi,a pd.111rx". au 'IQ n....,._... n '" *t

ucU.J..)Y i.i 111 aw :w"Umn;,w

".lliJnb Jl'Pllll" ""., RY "" n... 1t1*t.,..:m PlD (t-t*s..,... ~

HS).A.IYONnDI ws *sra ~

...... u n1.11 n I;' I ""'..

,.,,1111 "~"""' IP~

&.I.I 1 An*11.1 iuenu.11 lnDHl6 n lap ASDP pe;HfD.d ~..... ILl~I"..,91f; o; "'°"°'" ns* nNHI u, 111'°'"* M';:i'°"' mnp1.1 ft pen IQ llllf* wusu J.Nilit.LYJl.L J.Jn'fiiD il'iU.Y't1JJJllA* 911C,L

• a~fftb JIPUlln M Ul UO.;t.PLI nlQ.ICI' '/,)

P** n*1 put.,U,PLI -6..,,... szro pt1:in"Ct*t*s..,.,.ti NI) J.IYQMnDI "'\\(.)

un *&n puo~ pn u....,, a; eus *n -.i.1 **11111.1 iutnu.J.* 1no111&

o; ~

RICI~ " iuenu,. snNlll PIU'tD.ICI ""' *lfl' 16.rt&PI"..,1111 n.ID6JCI ns~ SftOHd Ul 111'-'*i*. aA'~'°.., n"""' n peai IQ llftfl WIJ.Sil J.DUYIU J.$n¥KXJ NOUrriu.01. *an PU1 NIJ.$U J.OC.Lnu ~

sna1n1 *au t*r*tt*t NOlJ.RidO MOi ND1J.1DW°' 9lllJJWii J.NJHJ.YiU 1.LSYP\\On ~noJSn

$~in~~; iAl.J..jYClCt1i

J/4,ll.3 SOLIO RACIOACT!VE WASTi

~IMtT!NG CONOtT!ON FOR OP£RAT!ON

• 3.ll.3.,,,e so11d r1cn..st1 syst.. sna11 be used fn 1cca~nc1 *ftft 1 pqoc!SS CONT'R01. PROGRAM to procus.. t rad1 a.ct he.. su ta lllHt sl'l1 i:ip*1 ng end bu rh I ground requ1 r..,,ts.

"~I~IILiiT: At 111 t111es.

ACitON:

1.

W1tl'I tfte prov1s1ans a1 tfte PROCUS CONTROi. PRQGRNI not Ht1sf1ecS, sus;encS sn1i:i-nis af dafe<:i1 vel1 process.a or dafta1 v1l1 ~dt1gld so11d rad1a.ct1ve *tstu fr-tW tJte s1u.

b. ilte ~rov1s1on1 of Soec1f1~t1ons l~O.l l1"i 3.0.~i 9.9.t.9~

IDP11~ble.

4.11.l. Tll* PWGC!JS C:ONT11a. '11G-111.111 119 usod t-s ti!* SIX.10!,!c.ITtCM af at lffst one l"'tOrtHnUthe test soec1w fl"Oll at

..,.1 )lfttft b~f Nd'I tyite af..c racS1a.cth*.. na (e.g., f11t1r sllicS991, SDen

,..s1ns, f

.1v1gor1tor ~.boric 1c1d salut1ons, lftd sact1uim sulfate so~ut1ons).

1. If llf'I test saec1111ft fails ta ver1 ty !01.IDIF?CATtON, tl'I* SOI.IO tFtC~ i!Cl't ot tM b1tdl under ~*st sn.11 be IUIPetUSN unt11 sud'I t1* IS acSd1t1on.1 test soec1ws ~

be aoc11ned, 1lt1rn1t1ve SOLIOIF!C~i!ON p1r-ca" Clft be oacarwtned tn 1ccord.lftca witft tl'le PROC!SS CONTROL PltCUM, Ind I subs*ent test ver1f1a S01.IOt1tCATtON.

SOLIOIF!C~itON of tfte Mtcn -

ti'!* be rtS.-d \\IS1"1 tM 11t1rtt1tht SOl.IOIFCAi!ON p1ramt1" tJIUNi nld bJ tl'le PRCC!U CONT'ROt.. PROGRAM.

b. tf tfte tn1t11l t1st saec11111tt fl"Oll 1 tsatdl of "t1111St1 fatls ta vel""ify SQ1.IDt1tCATtON, tfte PROC!SS CONTROi. PROGRNI sl'l111 cirov1de for. ene ca11e<:i1on and tasi1nt of rt0rtsant1t1ve t1st soec1mens frcm **~

consacut1ve b1iel'I of t~* 1111e t:tD* af.. i w1st1 uni11 1i 111st enrtt consKt&iht.1n1t11l tHt s;ecians d811onstrau SOLtOIF!~i!ON. iht PRQC!U CONTROL P~O~ Sl'l&ll b*.lft0d1f1td IS rtquirtcS, IS prevfded t~

S;ec1ftcat1on S.ll, to 1ssur* SOl.IOIFICAT!ON ~f subsequent ~1tcn11 Qf w1si1.

J/4 ll*L7 Amandlllent Na. @"

(

j I

\\

IUDtOACTtVE ErFtUEMTS 3/4.11.' TOTAL COS!

1.IMn'tNI eQNOn'tON '°" OPWTtON 3.11.4 T1'te annual (c:alendlr year) dose or dose ccasttmni to any Mt?oeD OF i1'1E PUILlC, due ta l"'llHstS of f"ld1Mcth1'Y ud f"ld1at1on, fl"Qm 1u*n1t1m fuel ~clt saurus shall be 1 tstied ta less tl'l111 or equl to ZS.,... to tl'I* tout t:lady or a,,, o,,.n (ucept ~

tnyl"01d,.n1cri shall be 11stUcl to less tl'lan or equ1l to 75.--).

AP'll CAI It.ITT:

A' a 11 t 1 mt

~Oii:

a. w1u ue c:alcul1ted doses fl"al ue l"thue of l'"ld1o.ct1.,. *i1r1111 1n 11.-1c& _. gu.aU1 1ff1uenu acaed1nt iwica in. 11stu of Soec1f1cai1an 3.11.1.21, 3.11.1.Zlt, 3.11.2.21, 3.11.2.Zlt, 3.11.Z.3a, or 3.11.Z.3b, ca 1ca11' 1 ons snau 1 ct bl aa t ncl ud1 nt lt1 rKC f"ld1 *'1

• cmrcr1 but1 ans

,,._ U..... cur Yn1U and f,._ OUU1dil SUl'l91 Uli&I ta at11"!1'1nt

.neiw u. 11.tu of u.11 SHC1f1cat11!!.llln been acaedlcl. tf sudl t' u. cue d11 1 t~ ifi 'tliltHi 1,.,.LAiioe't; P"PI"" w suOlrit to tJ'le C-1ss1on w1 1n a,s, pursuut ta Soec1t1ca,1* 1.1.2, 1 Soec1a1 ~~

Clld def1nes CM ca~1.,. 1c-:1a11 ta be ta* to r""1duc1 s.mseciueni l"tleues ta Pl"'l*W'li l"ICl&,.,....ca o'f acHG1nt tm *"' t1ants n

tnclllim CM scftecill*,_. 1ct11mnt canto,..,.ca *1i!I CM.~.,.

11.tU..

• 11111 Sp*1ca1 l8"t"t, 11 dlf1nlcl tn 10 C1I Pa~ ZG."lk, shall tnclua 111 111111111 tftd 11t1*U1 i!le ra~1t1an *2"1"" (daH) to 1 MIJl91R OI 'THI PUii.IC,,.. 1u*111fll* fuel c:tcl* sourus, tnch1a1n, 111 1ff'1...C pa~

1114 ltil"ld l'"lc&1n1on, tor il't9 calendar 1Hr tftat tnclua. u. l"tluse(s) cO'fVH bJ Ut1s l"'ttM~*. tt sllall also ascr1 t:I*

ltft11 ot ra~1"t1* IM cancMtrai10ftt of ra~a~1.,. *t1r111 trnahtd, IMI iM cause ot Ute aootu,.. ltffls or cancantrattons. tf

~.c1*Ud me(s) ac11a ue 1bcrle 11stts. n tf i21e l"'91t11*

~1*

,..ult1nt tn 'l1ol1,1a11* of '° en Pa" 190 nu nae 11,..*cty tieen ca~. U. Soec11l Rtta"' *snall tnclua 1 1"'9QUl9' for a v1r111u:a 1n ICCDf"Uncl witll in. Pf"G'ffstant of "2 en Illa~ 190. Sulllit:*l at tfte

,......,.. ts ~ans1daN 1 tt*l1 reGUn,, aria 1 var11nca ts grant.a uM11 ruff te:1.* an Ute l"'lqUU~ ts =-o11u.

Sill..iM

• UNtT Z 3/4 11-ta

J/£. lZ 3/'.l2.1

~ONtTORI~G P~O~~

1.Il"IitNG CONDITION FOR OP£RATION 3.12.1.

T'he rad1o1091c1l envf~nt111nt1l rnanftor1n9 ~rogrui sn1ll oe conduc~~ as splC1f11d 1n T1bl1 3.12*1.

AP,lICABtiITY:

At 111 t1mes.

ACTtON:

1. W1tJt tl'I*

0 r1d1olog1al tn'l1rownul 11Dftftor1~ p~tl"* not O.fn; J2 c:onducUd u spec1f11d tn T1Dl1 l.U*l, 4 '-' of I ih1n111 ;;,,.p

• .-..ctS,~ p~1re and sutlllit to tl'I* ca.1111on, tn th* Annu11

~0!1e&1 En'111"GnmttU1 O~el"at1ng lt1PGt"t required tly SpecH1c:at1on

~

~~>>**~* a ducr1pt1on of tl'le rw11ans fol" nat conducting eJ'I* ;:iroqr..

u l""ICtU1rtld and ~

pl1ns fol" pn'IW'lt1nt a 1"1Cul"1"9ftc1.

ti.

W1tJt tJte 11.,.1 of rad1acth1ty u tJte l"'ttult of plant 1f1"1u1nts tn lft 1n*1l"OIWUU1 SMP11ng mct1* at a siiec1f11d 1out1on ucH<&1ng tl'l1 retMt"t1nt 11.,.11 of T1bl1 3.12*2..,.,. a.,.,..~ o.,.,. any e&lenlUr qQt"tlr,@ 1,.. tf aJrlilMlll Eildl HHrt)°CPl"tPlr"e &ml *sutM11t to :.'It cmmtss1on *1tn1n la 011, pursu.~ ta SOec11'1cn1on t.9.Z, a S£tc11l RIPGl"'t tftlt tdent1f1u tftl ause(s) far acH<&tng th* ltll'ft(s) ind ct1f1nes tM cart"eet1.,. ac:1ans to be tlimt to-redua rad1ac:he 1f1"1umtts so tftlt th* Patlftt1a1 &nnull dot* ta I MOllU 0, Tr!E PIJSLIC ts 11u tl'IM tn. alendilr 1ur 1111'fu of Soectt1c1t1ons 3.11.1.z, 3.11.2.2, and 3.11.2.J.

Wl'left lllal"t t111n ane of tl'I* raa~onucl 1ctes fn TaDlt 3.12*2 arw dlttc:ld tn ttt. Slt!Pltng lllld1Ull, tn1s r1port s~all be suc.1 ttld 1 t:

c:ancentrat1on (1) l"'tParttnt 11.,el (1) c:ancentrat 1 an ( 2) rwpart1nt level (Z)

• *** >l..O w:,en rad1onuc1 tdu other tl'llft tl'lase fn Table l.lZ*Z al"t ct11:1cud 1nct 1rt tM rault af plalft 1f1"1uents, tJ'l1s l"'tOG~ 1n111 be sl&Oll'ttild tf :l'l1

~auni 11 l &nftUI 1 dGH ta a llllllCl*r af tl'le IND 11 c f s IQUI 1 to ar grtt u r S,\\Lt'f

• UNIT Z 3/4 lZ*t Amendment ~a. ~

J1,.1z

~AOIOLOGICAL ENVtROPIM!N'T'AL ~NtiOR!~G 3/4.12.1 MONITORING ~~O~

1.tMtTtNQ ctlNOt!ION 'OR OPOATtON ACTION:

(Ca~ 'd) tn111 tn. cilen~r 1**r 11*1ts at S~tc1f1~t1ans l.11.1.z, 1.11.2.2, 1nd 3.11.Z.3.

1'111s r.pai-: ts nai ~1 red ff tn* *uul"ff lt'ftl at ria1act1Y1'1 wu noi tM resiilt of 11t1nt tf11uenu: hawHtr, tn sur:l'I lft t'ltflie tn. r:anci1don sn1l l M rtfaf"'t.S lftd daSCt'1b.C 1n UI* Annu&1 bdj 01at'fCl1 lnY1~u1 Oper1i1 "' RIPD"'*

r:.

W1tlt ml\\ or fl"'tlb 111'1 "'9tlb1t 11111111* 11111Y11llb1* fl"al an* ar *111ar1 of i11e 1i1111111 1acat1ons ~1r"H bf Ta11 3.1%*le' 1dent1'1 1aut1ans tar oau1n1nt rtt1l1c-.nt H_.1a Md add i!t* ta ii. rad1alof1cil tnYf rOIW'Ul w1tar1nt Prov* wiitttn 30 a,s. nte spec1 f1r:

1oc&i10M,,.. llftfdl SMIPlU.. re 1111Hlt1M11 -

tft* M al~ed f1°9 iM _.turtnt Prat,...*

fl.=

Qi cana11 l1w1t R*on iii,.rsuant io Soec1 f1citton

'!.=:: ;;;;; *==~

~.

1a.t1fl1 tJ1e c&uM of tne 1111Hlfl&bt1tt1 of HlllllU iftd tl'tl l.E/ -,,. focat1111(1) for altU1n1nt,..,11c1 ll"C SMPlll tn tlle nut S..tlftftUl bd1aict1'ft lf'f'1U8flt **,.... **Por"t.

tnc:tua '" tM_l'"tPGl°'t 1 1"'1'111.ct t1gure(s) and UDlt for tn. OGCM l'"tf'1tc:i1nt t!tt,,_..

10Cd1an(s).

d. n.. pl"OY1s1ons of ~1t1~t1on1 3.Q.l llld 3.0.4 are noi 1ppltr:1011.

SUAV!Il.URC! UOU tRODTS 4.lZ.1 The m1olot1ca1 lft'f1r-*nta1 mwttar1nt s-1* snall b9 r:allKted llUl'"11Wti to T&bl* 3.lZ*l fl"all tM 1acat1ons spec1f11d '" th* OCCM IM 11'1&11 t:I*

1n1tyi..a*CN1"1Uani io tn. ~1.....n~ of T1al1 4.1%*1.

SAUM

• UNIT Z 3/4 1%-Z

~ n;o/'

-u

'2f !S>( CJ

/, "'r>'(t 'bd

_J~1<(l'I

~!).J....

• ~a;dwl/5 _,~>;;)"

G,,.~';rl.,.~Jr J 0-j "D

51.

rsrJ

~, _,( ttt/

p) *':J d ;., o / x a:

_j <>

o>1/'7f.

~ 'r,,-J 5..'.J.o Ja-f t:l(>?

Gv:'71UJ.Jf 011 :tI.**nt"' ttl 1n* IJJ ~ 'I'll *n1*1 Jal'" fi*t.,PP JoJ (*t I "l7 zOI _* t zOI

• l col

• l OL

,..

• l Ol M

tOI

• I

'°' *,.

OI Ot zOI

• I t

(cf!

zOI * *

• z zOI

• t t01

• 1 zOI

• t tOI

• t tOI I I tOI x. I zOI

• t tOI

• J tOI

• I hJtOI

• l (18" 'IJ/l,.J (1* **i/1JdJ

,,.,,,., IH'9.IO lpnpDJ. pooj

~""

'lllf

~1 tnJt1Jt*.. JoqJtY Jll'ft SJldHYS 1'111JHllOllAllJ 111 SllOllYllllJJllOJ AllA_llJYOIUYI WOJ SlJftJl !Jtll lllU*JI z-z1*c 11n1 ot1-*1-*w f(l-IJ t(l-IJ 1u-1

• &-Q-Jl 9,-.,

09-0J gg-oJ gg-*J H-UH t-H

'~'"

0 7-...

c I c

J M

N t-z:

~

N N *

~

N (I)

Andy di yrou beU 11-l Hn-54 h-!.'J Co-!18, 60 ln-6!.

lr-~-95 1

I-Ill Cs.-ll'"

Cs-111 P*-l*-140 U*t*r (pCl/I) 4 2..J£)

IS lO IS

(.

10 1*.

15

\\

'*~ BJ IS 18 15 IABU 4. ll-1

. (~ bJ HAllHUH VALUES fOI 111£ LOWU llHllS Of OUECllOll*(LlD( '-~

Alrbor** P*rtlcul*t*

fhla Hiik food Preduct*

Sediment or &.*** (pCI/* )

(pCl/lg. wet)

(pCl/I)

(pCl/lg. wet)

(pCl/t:g. dry) a

• ao-2 uo 260 llO 260 1

• 10-2 I

60 5

• 10-2

. llO i5 60 150 10-2 150 II 80 180 l5

r~BLE £.12*1 (Cont'd)

.~SL! '40TlTlON 1 Requ1r"l'd d*ttct1on ~p1b11ft11s for th1rmo1W11n1sc1nt dos11ft9t1rs used for 1nv1rona.nta1 1191su~nts 1r1 given in ~1~11tor-J G~1d1 4.l3. Rtv. l, July l977.

a Th* u.o is d81'1ned fn i1b11 _4.11-l.

d L. iD t=Oi Jr~" 'Ji;~

o.I pa fl.. vQ.y e.x ;5 fy.,

a.

S~L~

• UNIT Z

"'IQ.J..t:!r

~atnple.s. rr= no J;-.r.ft;;,'J i.)q.-f~.-

,,.ct lr.t. e o -F I 0 f C::.;. / _/

ffTl '47 6 e

'~ea~

ll' u-10

RADIOLOGICAL ENVIROHM£NTAL /'IONITORING 3/4.12.Z LANO USE CENSUS LI~IT!~G CONOIT!OH FOR O~RATION 3.12.2. A hnd use ~nsus shall tie canduc:tld 1nc:t shall fd1nt1fy within a dfstanc:a of 8 km (5 miles) th1 1oc:1t1on 1n 11c:h of tl!e 15 11111teorologic1l s1ctors of tha nHrHt lll'flk 1nfm1l,. tl'le nHrHt resfdenc:a ind the n11rest gard1n* of gr11t1r than SO ml (500 ft') produc:fng broad lHf ve91ut1on.

(For tltvattd releases 1s d1ffned fn Rt9Ulltory Gu1dt 1.111, Revision 1, July 1977, tl!e land us* ~nsus shall alsa fdtntffy within 1 distance of S k~ (3 miles) the 1oc1t1ons fn Hc:h of the 15 rrauorolog1cal sectors of 111 nrtlk 1n11111ls and 111 gardens of 91'HUr than 50 m2 l""du.c:1ng broad 111f ve91Utfon.

APPlICA8ILITY:

At 111 t11111s.

ACTION:

1. With 1 land use cansus 1dent1fy1ng 1 l"cat1on(s) that 111lds 1 calculated dose or dose mllll1ta.ni gr'Htr than tl'le values curr1ni1y being cal cuhtlG fn Spec1 f1c:at1on 4.11.2.3, << "*u a' a 1 I !!I"'" Ti~

'2d'#pti. fd1nt1fy thl nw locat1on(s) 1n tl'le next S1fll'f1nnual Rad1oac:i1ve Ef1'1u1~t R1l11S1 Report, pursuant ta Spec1f1cat1on 5.9.l.~

• o.

Wfth a lind use cansus 1dent1fying 1 lacation(s) that yields 1 calcuhtad dose or dose caftlll1ta.at (vii) t'- saaw upasur1 pathway) 20 percent gr11t1r than at a location fro* wnich Simples 1r1 currently be f ng o bU 1 ned f n 1 cca rd1nca *i th Spec 1f 1 cat f on 3.12.1, 1dd tl'le new 1ocat1on(s) to tl'lt rad1ological tnviron1111nt1l nanitar1ng ?i"OCJ"llll within 30 days. The s1~lfng loc:at1on(s), uclud1ng tM control station location, l'laving th* lo*st calcuhtlG dose or dost mllWl1tlT9nt(s) (vh tl'le samt txpasurt pathway) 11111 bl del1tld fro* this nan1tor1ng program afttr Ociablr 31 of the yHr fn wftich this land use census was conducted.

su1ni ta S c1f1

, 1dant1fy the new 1ocat1on(s) 1n the next S1lll11nnu* l R1d101ct1 ve Eff1uant Rel 1111 Repart and 1 l sa 1 ncl \\Ria 1 n th*

r1part 1 i-ev1sed f1gul"l(S) and Utile fnr tl'le OOCM ren1ctfng the new 1ecat1on(s).

c. n. prov1s1ont of Spec1f1cat1ons 3.0.3 and 3.0.4 art nat 1pplf c1bl1.

WSr"Oid lHf ve91t1t1on Sl!llDl fng of at 111st tt'lrff d1ff'trtnt kfnds of vegeUt1on may bl perfor!IWCI at the SITE BOUNDARY fn 11cn of tlG d1f'f1rtnt d1r"IC:t1on stc=rs with the 1'11gl1Ht prtd1cttd 0/Q fn 1f1u-of tl'le gardan census;.

Sp1c1f1c1t1ons for tiro1dl11f vegetation sa~11ng fn T1al1 3.l2*1.4c shall bl 1'o I lowed, 1 ncl udi ng 1n1lys 1 s of cantro 1 sampl IS.

SAL£M

• UNIT 2 3/4 12-11 Amendment No.~ f I

~ACtOLOGtc;L ENV!RONMENT~L ~N!TOR!NG J/4.12.z wca U5E CENSUS

( CcM Id)

SURV!IL~NC! ~!OUIRD1!MTS 4.1%.%

The hncl use ctttsl.IS sh111 tie conductld dur1 n9 tl'I* grcw1 ng seuon it l11st anca per lZ.artins usi~t tJut 1nfol"llllt1on tJ'l1t w111 pro*1d1 tl'I* best l"'ISU 1 ts, su~ u bf 1 daor*to-<toar SUl""fJ, Hr111 sun'1, ar bf consu 1t1 ng l oc1 l 19r1cultur1 autnor1t1a. 'Ml* l"'Uults af tJ'I* land uH cansus shill tie tnclud-4 1" tft* MINI t R1ct1atof'fCl1 l,n'W1 ~u l Op*rU1 "' R*,a~ purs&Mnt ta S,.c1f1C1tion e.1.1~. *

(j>

SA&.!M.

• UN IT Z l/~ tZ*tZ

.-ncillent ~o. ~

~AO tOLOG IC~L ENV t~ON.. ~i,!.L."'ON troR ! ~G J/4.lZ.l.

!~i!~l.)80AAl'ORY COMPARISON ~~O~AM I. !MtT!PfG CCNO tTtO.N FOR OP~.A i!ON l.lZ.l Analyses snall bt performed on rad101cttve ~teri1ls suoolft<S 1s :1t"'"! of 111 Inurl 1t1ar1tary C.*r1 son Pr09ru wnt ~ hH been 1oo~vtd ~ ~.,, C:nsni u 1 on.

APP~Ic.lltLITY: At 111 t1111s.

ACTtON:

Wi ta iftilyHI not 1:91 n9 oerlol"ft!IH I! l"lqt!f l"ff &DGYI' ~a~ tn*

carr"WC1ft 1c:t1an1 Uhn to pr..,ent 1 recurT"lftca to tn* C=-iss1at1 fn tne Anna.I R1d1alag1C1l ttiv1ro111111nt1l Operating R_,ari ~r,uant ca Spec1f1Clt1an S.9.1.~

b. Th* prov1s1ans af Spec1t1cat1ons 3.0.l 1nd l.0.4 **,.. nat 10011~1Dl1.

4.12.l A s~r, af tnt r.s11lts a~11nect 11 p1~ of cne 1~aft ~u1,..d tntarhbaruory Ce11D1r1 son P!"Q9ru Md f n 1ccaranca wf tn tn* OCC4 sn&T 1 ~*

tncludlG fn tne Allnu1l Rad1alag1ca1 Env1ro,,..,.~I Ooerat1ng R1oari ou,.,uant==

S-tla*1on 1.1.1;!;.

s.a1.::,..,.

• UNIT 2 J/4 lZ*ll y

~tndment ~o. 2:9"

/

• Pow!Jl DISTRIBUTION LIMITS 3 4.2.2 and 3 4.2.3 HEAT FLUX HOT CBANN!L FACTOR P RCS PLOW RAT! AND NUCI.!AI DmW.PY RISE BOT CHANNEL FACTOR Continuad event. ni. pen&lties applied to yNitil to account for Rod Bow (Pirur* 3.2-4) as a function of buTnup are consisten~with those described in Mr. John 1. Stolz's (NltC) latter to T. M. Anderson (W**tinghouse) ~ted April S, 1979 and W 8691 Rev. 1 (partial rod bow t**t ~ta).

When an F maasurament is taken, an allowance for both exp*rimental error and manufactur~ng tolerance lllU9t be made.

An allowance of 5% b appropriate

• for a full cor* map taken with the incore detector fluz mappina system and a 3% allowance is appropriat* for manufacturina to.Larance.

When RCS flow rate and ~ are 111&&9ured, no additional allowances ar*

necessary prior to compar!son with the liaits of Pirure 3.2-3. Mea*uremant errors of 2.2% for Ra.actor Coglant Syst.. total flow rate, 0.1% for feedwater venturi foulina, and 4% for r~ have bean allowed for in the d*t*l'llination of the desian DNBR value.

The mea*uremnt error for Ructor Coolant System total flow rate is ba**d upon performina a precision haat balance and uaina the r**ult to calibrate the RCS flow rate indicators.

Potenti_al foulina of the fudwatar venturi which *i1ht not be detected could bia* the result fro. the precision ha.t balance in a nonconservative manner.

Therefore, a pen&lty of 0.1% for undet*cted fouling of the feedvater venturi is included in"Pirure 3.2-3.

Any foulina which might bi** the RCS flow rate measurement areater than 0.1% can be detacted by monitorina and trandina various plant performance par... ters. If detected, action shall be taken befor* perforaina *ub*aquant pracision heat balance measurements, i.e., either th* effect of tha foulinl shall be quantified and compensatad for in th* RCS flow rate measurement or the vmituri sh.all be cleaned to eliminate th* foulina.

Tha 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> p*riod surveillance of indicated RCS flow is sufficient to detect

~~

flowdagradation which could lead to operation outside the accaptable region of oparation shown in Piaur* 3.2-3.

0 The radial peakin1 factor 1 (Z) i* measured periodically to provid* assurance that th* hot channel facto;!?lQ(Z), r... in. within its limit.

The 'xv limit for RAT!D TH!RMAL POWll (~:~), aa providad in the Radial Peakina lac~or Limit Report per specification 6~.1.J!.9-., vu detemined fro. expected power control maneuver* 9ver tba full rana* of burnup conditions in th* cor*.

3/4.2.4 Q!1ADJlAHT POWER TILT RATIO Th9 quadrant power tilt ratio liait a**ur.. that the radial power distribution.. ti*fi.. th* d**ian valu.. u.aed in the power capability analysis. Radial power distribution maa.ur-..nts ar* made durin1 startup tasting and periodically durina power operation.

SALIM - UNIT 2 B 3/4 2-S Amendment No. 64 Effective Date:

November 3, 1988

REACTOR COOLANT SYSTEM BASES 3/4.4.6 STEAM GENERATORS (Continued) fie Cl PP /;c.d ~I-.<

!tiM~~~n-&1~~...+-~HH!~~:e.i-1.IS~im--~-P-1-an:r-E~~n-&1~--l ~ec.. f;,. n.>

.> F 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.7. 1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary.

These detection systems are consistent with the reco11111endations of Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection

Systems, 11 May 1973.

3/4.4.7.2 OPERATIONAL LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 GPM.

This threshold value is sufficiently low to ensure early detection of additional leakage.

The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage frc11 known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

The CONTROLLED LEAKAGE limitation restricts operation when the total flow from the reactor coolant pump seals exceeds 40 GPM with valv* 2CV71 fully closed at a nominal RCS pressure of 2230 psig. This limitation ensures that i*n the event of a LOCA, the safety injection flow will not be less than assumed

• n the accident analyses.

The surveillance requirements for RCS Pressure Isolation Valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.

Leakage from the RCS Pressure Isolation Valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.

SALEM - UNIT 2 B 3/4 4-4 10- c.PR-S-o. 7 :i.

REAC70R COOLANT SYSTEM BASES 3/4.4.9 SPECIFIC ACTIVITY The limitations on the specific activity of the prim*ry CQolant ensure that the n:sulting 2 nour doses at the site boundary will not 1xc1td an appropriitlly sull fraction of Part 100 l i11it.s following a stlu generator tuce rupture accident in conjunct~on witn an assumed st11dy state 13riNry-to-second1ry st1a11 generator 111K1g1 rate of 1.0 GPM.

Th* values for th* limits on specific activity rtpr*sent interim limit.s based upon 1 p*rametric evaluation by the NRC of typical site locations.

These valu11 1r. conservative in that specific site paraaaters of the S*l1S site, such as sit1 boundary location and meteorological conditions, wer. not consfder9d in this evaluation.

The NRC is finalizing site specific criteria which will be used as the batis for the reevaluation of the specific activity limit.s of this site. This 1"9evalu*tion may result in higher li*its.

~TAI A'TlQN s~i.. e"i "ll'lliiiiAg ?QWER QP&RATIQN ii ea,.ii,.ue fer li11~\\1i ti111 !'IPhls witJll tA* 'PiMpY ;111Mi 1 9 9,Hif1; *-='h'it.y i'PH\\IP iAaA l._Q 1=161/ara SQSE EQl.HVAlBfT I*31, l!lt~t wi~ni" ine allowable H11i~ Sfte\\\\" e" Figure l.4*1, aaae.. aa1t.1s,a11i-l1 iadiR* s'ikiAt 'AeAa.. AaA wAi;A 1ta1J ;;;wp fe 11 ewi "' eJllaflgH 1 A nliR.U.AI. i;10WiR.

Q,1Paii QA wi ~ 5,Hii f 1; H~i Yi~ l 1v1l1 1.-;11i:fF19 1.Q ti'C1/gsra* QQii iQUIVAl.iN+ I-lil aw' w;"";" \\Re li11it.s sli\\ew" IA Fi~UPI 3.4*1 ~U5' B* PtSiPi;i1a ';Al IWIPI 'AIA iQQ AIWPI ~*p YliP (1~ia,oxi-111,aly lQS ;:f tA* WRit 1 1 yHPly 1ia1nt.iR9 t:f.. ) llAH \\A* a;\\hii\\;' laYlh 1ll1w1i ;y FigwP1 ~.4-1 iA;iae11* t~* 2 Rewr tAyre;a aes1 a' tJ111 s;t1 eawAaapY By i faet.IP af W' ta 30 ftll;wiAg i ia1siwlat1i S\\i.. i1R1Pli8P tWDI ~W~tWJ'4, TR* Pe~aAiAg af s.. w11t.h** t:f* l\\'8P iQQ "'w" iR iAY i MFlt.A ;;A11;wtiv1 i:iaric:id,._;tt:i 9Pt1t.*P tAM 1.Q 1i1'i/g11a11 QQii iQUIVAw:T' I-131 will a11ew s1:1ffis;eAt

\\i~* P Sa1111;ssieR 1Y1lw1*ie" 1f tA1 eiPe~1ia,.e1s ~Pier ii Pea;AiR9 \\Al

\\.eee ~e~r l ; 111; '*

Reducing T to 1111 than S00°F prtvtnts the release of activity should a steam g1n1ratS~gtua1 rupture sinc1 the saturation pressure of th* primary coolant is below the lift pr.ssurt of the atmospheric ste.m 1"91i1f valves.

The surv1illanc1 rtquir... nt.s provide adequate assuranc1 that 1xc1ssiv1 specific activity l1v1ls in th1 priury coolant will bt d1tect1d in sufficient timt to take corrective 1ction.

Information obtained on iodine spiking will be us1d to a~s*ss the parameters associated ~ith spiking phenomena.

A reduction in frequency of isotopic analyses follo~ing po~er chaog1s iillY be permissible i!

justified by th* data octained.

SALEM

• UNIT 2 8 3/4 4*6 r

.:. : '*1 : 't : 3 - :.:. - : * ~ : : 'I -

6.1.1 The General Manager - Saiem Ooerations sna1i oe resccrs':':

facility operation and snail aelegate in writing tne successjcn :c responsibility during nis aosence.

.:,...,.. :. ;,* ~

6.1.2 The Senior Nuc'~ar Shift Supervisor or, during his absence from

~~e Contra 1 Room, a des i gr.H.ed i na iv i dua 1 sha 11. be rescans i bl e for tne Centro' Room command function. A management directive to this effect. sigr.ea cy

~e Vice President and Chief Nuclear Officer, shall be reissued to a** itatior personne 1 on an annua 1 basis.

6.2 ORGANIZATION 6.2.1 ONSITE ANO OFFSITE ORGANIZAT:ONS Onsite and offsite organizations shall be established for unit ooerat~cr a~c corcorate management, respectively.

The onsite and offsite organizat'crs sna.

include positions for activities affecting the safety of the nuciear power plant.

a.

Lines of authority, responsibility, and communication shall be established and defined from the highest management levels througn intermediate levels to and including all operating organization positions.

These relationships shall be documented and updated; as appropriate, in the form of organization cnarts, functional descriptions of departmental responsibilities and relationships, ana job descriptions for key personnel positions, or in eouivalen~ for~s of documentation.

These reouirements shall be documented in the Salem Updated Final Safety Analysis Report and updated in accorcar~:

with 10 CFR S0.71(e).

b.

The General Manager - Salem Operations shall be responsible for overall facility safe operation and shall have control over tnose onsite activities necessary for safe operation ana maintenance ci the plants.

c.

The Vice President and Chief Nuclear Officer shall have coroorate responsibility for overall plant nuclear safety and snall tak~ an; measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plants to ensure nuclear safety.

d.

The individuals who train the operating staff and those who car*;

out health physics and ouality assurance functions may report :c :~e appropriate onsite manager; howev.er, they shall have sufficient organizational freedom to ensure their independence from operatin; pressures.

6.2.2

~AC!LITY STAFF The facility organization shall be subject to the following:

a.

Each on duty shift shall be composed of at least the minimum sni~:

crew composition shown in Table 6.2-1.

SALEM - UNIT 2 6-1 Amendment No.76

FACILITY STAl'f (Continued)

b.

e.

Ff,.

At laut one licen.ed fUal i* in the reactor.

Senior Reactor Operator tiae*.

erator shall be in the control room when In addition, at least one licen.ed shall be in the Control Room area at all h health p~1ie1 teel:Klleiaft* shall ee en 1ite wtien f~el is in-ehe reaetel':

~

CORE ALTERATIONS shall be ob*erved and directly supervised by a licensed Senior Reactor Operator who ha* no other concurrent responsibilities during this operation.

A site Fire Brigade of at least 5 member* shall be maintained onsite at all times*. The Fire Brigade ahall not include 4 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

The amount of overtime worked by plant ataff members performing safety-related functions must be limited in accordance with the NRC Policy Statement on working hour* (Generic Letter No.

82-12).

The Operating Engineer, Senior Nuclear Shift Supervisors, and Nuclear Shift Supervisors shall each hold a senior reactor operator license. The Nuclear Control Operators shall hold reactor operator licenses.

1Ji*

The Operations Manager shall meet one of the following:

(1)

Hold an SRO license.

(2)

Have held an SRO license for a similar unit (PWR).

The ae*lth physies teeanieiaft aad Fire Brigade composition may be les* than the minimum requirements for a period of time not to exceed 2 hour* in order to accommodate unexpected absence of the he*llft*

phy1ie1 teehftieian and/or Fire Brigade members provided immediate action is taken to restore the healtft paysies teehnieiaft anG,'er Fire Brigade to within the minimum requirements.

SALEM

• UNIT 2 6-la Amendment No. 89

Figure 6.2-1 CORPORATE HEADQUARTERS ANO OFF-SITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT (Deleted)

SALEM - UNIT 2 6-2 Amendment No. 76

FIGURE 6.2-2 FACILITY ORGANIZATION (Deleted)

SALEM - UNIT 2 6-3 Amendment No. 76

POSITION SNSS SRO STA

.NCO EO/UO TABLE 6.2-l MINIMUM SHIFT CREW COMPOSITION SALEM UNIT 2 WITH UNIT 1 IN MODES 5 OR 6 OR OE-FUELED NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES l, 2' 3 & 4 MODES 5 & 6 la la lb none lb none 2

le 3

2 Maintenance Electrician 1

none e+J. f'rg, Tec.ba;,:4.,

I c...

I Q.,4.

WITH UNIT 1 IN MODES l, 2, 3 OR 4 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES l, 2, 3 & 4 MODES 5 & 6 SNSS la la SRO lb none STA lb none NCO 2d 1

EO/UO 1

Maintenance Electrician 3a 1

none e.o.o/. ~ro. T~c./,,,;c:ari I ""

/&l

£/

~/

§:./

Individual may fill the same position on Unit 2 Individu~l who fulfills the STA requirement may fill the same position on Unit 2.

The STA, if a licensed SRO, may concurrently fill the SRO position on* on* unit; the other unit also requires a qualified SRO on shift.

One of th* two required individuals may fill the position on Unit 2, such that there are a total of three EO/UO's for both units.

One of the three required individuals may fill the same position of Unit 2, such that there are a total of five EO/UO's for both units.

tJ:. f f1'7~Pd ;F i:Pfl-f'??ac f.,f.J

.:c f"-41' ale-~"~

SALEM - UNIT 2 s-,4F Amendment No. 33

SNSS SRO NCO STA EO/UO TABLE 6.2*1 (Continued)

Senior Nuclear Shift Supervisor with a Senior Reactor Operator License on both units.

Individual with a Senior Reactor Operator License on both units

( no rl!'li 11 y, a Nuclear Shi ft Supet"ri so r )

• Nuclear Contn>l 0pet""atar with a Reactor Operator License on both units.

Shift Technical Advisor (if licensed as SR011 may t:e assigned duties as a Nuclear Shift Supervisor).

Equip1111nt Operator or Utility Operator.

Except fbr the Senior. Nuclear Shift Supervisor, the Shift Crew Composition may*

be one less than. the minimum requirements of Table 6.2-l for a period of time not tc exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.in order to accormcdate the unexpected absence of on~uty shift crew ITl!meers provided that inml!diate action is taken.ta restcre the Shift Crew Composition tc within the minimum requirements of Table 6.Z-l.

This provision ciles l'Xlt permit any shift crew i:csition to be unmanned ui:,ion shift change due ta an onco!'1-ing shift crewpersan 's being late or absen't.

During any absena of the.Senior Nuclear Shift Supervisor from the Control Room area while the unit is in any MOOE, an individual with a valid SRO License shal 1 be designated to assume the Control Room command function.

SALEM -

UN tT 2 6-S*

~mendment No. 33

\\

ADMINISTRATIVE CONTROLS 6.2.3 SHirt TECHNICAL AJ)VlSQR 6.2.3.l '111* Shift Technical Advisor shall

~Shift luperviaor on matters pertaining

~

~u~a operation of the unit.

serve in an adviaory capacity to to the engineering aspects assuring 6.2.3.2 The Shift Technical Advisor ahall have a Bachelor'* Degree or equivalent in a scientific or engineering discipline with specific training in plant design and responae and analysis of the plant for transient* and accidents.

6.3 fACILIIY STAFf QUALIFICATIONS 6.3.l Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI NlS.1-1971* for comparable positions and the supplemental requirements specified in Section* A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licenseea, except for th Radiation Protection~Bagineer who shall meet or exceed the qualifica ions of Regulatory Guide 1. 8, September 1975.

it1Ji'lio/uaf c/eG1nafttf as 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be coordinated by each functional level manager (Department Head) at the facility and maintained under the direction of the Manager - Nuclear Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI NlS.1-1971 and !..ppeaaia *h* af 10 CFR. Part 5~ aad 10fte s~pplemeft~al recp.iiremenu spec:ifhd in S.c:tion.1 A and C of lnc:lo*"'I'* 1 ef ae Mana :u, 1980 NaG letter te all lieensees, and saall iaelude faailiarieatiQn wit&

relev&Rt infistey eperatieRAl eKp*riacwe, 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager -

N~elear Training and shall meet or exceed the requirements of Section 27 of NFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly.

<;;+I!. fh>fec. fio"

• The Opera~ions Manager shall meet one of the following:

(1)

Hold An SRO license.

(2)

Have held an SRO license for a similar unit (PWR.).

SALEM

• UNIT 2 6-6 Amendment No. 89

ADMINISTRATIVE CONIROLS 6 I 5 REVIEW AND AUPIT 6.5.l SIAI!ON OPEBAI!ONS REVIEW COMHI'tl'EE (SQRC) fUNCIION 6.5.l.l The Station Operations Review Committee shall function to.advise che General Manager - Salem Operations on operational matters related to nuclear safety.

COMPOSITION 6.5.l.2 The Station Operations Review Committee (SORC) shall be composed of:

Sr!E rAJsear To "* s; 1. ~

Memeu* aRll Viee GfiaimaA; Operating Engine*r Keaee!':

Kemiser:

Kaaluu;;

Tacbnical i"&i"eer Ma*IHlri Memee!':

e:r hi::I fiHi:pee.

ALTEBNAIES

6. s I l. 3 All aleet"!'taee memeeH shall ee appeineee in °JJ'Ei:Eb:g ey &Re iQRS 61'lait'!!lan.

a.

!Jiee ShaiaeR shall ee mem8BE'& ef S;a;hR maRage1aeR;,

1'.

!le mere !he ewe a:lee'E'RACaa ;a meue:n &'Rall. parti;ipata u uo"" i:i5 memeers i:ft sgae aeeivieiee ae &fl'! ene 111eeeieg,

e.

hlee!'fteee appeifteees will enly represene eheir respeeeiue eepal'H81ll.

a.*

hleeftNl&ea fer memee'Es will Re& make Wf1,a!'e ef ehe veeiRg ~~eEUiP.

vheft ehe memeers ehe aleerfteee represeftes is alse,'Ee&eRC.

MEEIING fREOUENCX 6.5.l.4 'nle SORC shall meet at least once per calendar month and as convened by the SORC Chairman or his designated alternate.

OU ORUM 6.5.l.5

'nle minimum quori.Jm of the SORC necessary for the performance of che SORC responsibility and authority provisions of these technical specificacions shall. consist of the Chairman or his designated alternate and five members including alternates.

St~ :!lllSiR.i /O '* S. /. 5' SALEM - UNIT 2 6-\\'

Amendment No. 3 3

INSERT TO SECTION 6.5.1.2 Chairman:

General Manager - Salem Operations Member and Vice Chairman:

Maintenance Manager Operations Manager Technical Manager Member and Vice Chairman:

Member and Vice Chairman:

Member:

Radiation Protection/Chemistry Manager Member:*

Member:

Radiation Protection Engineer Chemistry Engineer Maintenance Engineers Operating Engineers Member:

Member:

Member:

Technical Engineers (Group Heads)

Member:

Onsite Safety Review Engineer ALTERNATES 6.5.1.3

a.

b.

c.

. d.

INSERT TO SECTION 6.5.1.3 Alternates:

Alternates shall be appointed by the SORC Chairman in writing.

Only designated Vice Chairmen may act as Chairman of a SORC meeting in the absence of the General Manager -

Salem Operations.

Alternates shall only represent their respective departments.

The Senior Nuclear Shift Supervisor (SNSS) may act as an alternate for the Operations Manager or an Operating Engineer.

The SNSS may also act as an alternate when the Operations Manager is acting as Chairman.

a.

b.

INSERT TO SECTION 6.5.1.5 No more than two members or one member and one alternate from any individual department will make up_

part of the voting quorum.

If the Chairman for a meeting is a Vice Chairman, then up to two additional members from the same department (or one member and one alternate) may be part of the voting quorum.

: *~ :.. : ; -: : -:. :: : :.. -: : -:

6.S.1.6 The Station Ooerat~ons ~eview :ommittee snai;

~e '"esoors*:*e --.. *

a.

Review of: (1) Station Administrative ;rocedures aria c~anges :-e.. e.

r:~-;::~~::::;;;~;-;.;;-i.~~~a~n~d;L,.'(2) Newly created orocedures or changes to existi~g orocea~,.es reictire ~ 1oc.FRS"0*5' that\\fi,welve* a si~i:iifieai:it safety iss1:11e as aescrioea in Sec:'o?i 5"1. Fefy evt1r!uaf~ori

6. 5. 3. 2. d.

ct..~ H.e *e fo.fl.Q. t re3u ;~ o..

/QC.FR S"O.S-'f Sq.f:ef e !IQ lut:l -/-,'o,,

b.

Review of all proposed tests and experiments that affec: nuc'ear safety.

c.

Review of all proposed changes to Appendix "A" Technical

.Specifications.

a.

Review of all prooosed changes or modifications to plant systems -..

eQuipment that affect nuclear safety.

e.

Review of the safety evaluations that have been completed un~er :-e provisions of 10CFRS0.59.

f.

Investigation of all violations of the Technical Specifications including the ~Fe~aFatiai:i aA~ fe~'aP~i~g ef reports covering evaluation and recorrmendations to prevent recurrence te t~e ~iee.

P,esideAt aAd C~ief N~eleaP Qffie1P aA~ t~e GeAe,al Ma~age, NijeleaP Safety Review.

g.

Review of all REPORTABLE EVENTS.

h.

Review of facility operations to detect potential nuclear safetJ hazards.*

i.

Performance of special reviews, investigations or analyses ana reports thereon as reQuested by* the General Manager - Salem Operations.eF GeAeFal MaAageF

• NYcleaF Safety Review.

j.

le..

l.

Review of the Facility Security Plan* and implementing proceau,.es a'":

Revi e\\L, or-lnvo/.. e a..

po~;i'(-;q/

c.l"eo'~,*ri Hie eFF"ec-f.'ve'1es.s oF t4e pla.11, ~er 10 c fl= R. so. EJ'I lP ).

Review of the Facility Emergency Plan and implementing procedures and or ;nvol~.... f"fWi!11fi14/

e.:.r~f' in -flie e-FfV~ ;,,..,o

.of= riie pftM, per /OCF~ SO.G'f {f).

Review of the Fire Protection Program and implementing crocedures and swbmittal ef reeemmeAaea el:iaAges ta tl:ie GeAeFal MaAageF N~elear Safety Review.

m.

Review of all unplanned on-site releases of radioactivity to ~~e environs including the preparation of reports covering evaluatio~.

recorrmendations and disposition of the corrective action to oreve'":

recurrence aAa tl:ie feFwaFdi~ tRese FUCH'tl to Oe !Ji ct-- Pees' :ec:

iR~ C~ief N~eleaP QffieeF aAa tl:ie Ge~eFal MaAageF Nije,~aF Sare:,

~ev i e*.,.

SALEM

• UNIT 2 6-8 Amendment No. 76

Pr-o~**ole rec.omtfle~f.011s RESPONS:SIL!T:ES (continu~d)

n.

Review of changes to the PROCESS CONTROL MANUAL ana tne DOSE CALCULATION MANUAL.

SORC REVIEW PROCESS 6.5.1.7 A technical review and control system utilizing qualified revie~e~s shall function to perform the periodic or routine review of procedures and changes thereto. Details of this technical review process are providea in Section 6.5.3.

AUTHORITY 6.5.1.8

a.

b.

The Station Operations Review Committee shall:

ino/ir;.a.hn9

-Reeemme~d to the General Manager - Salem Operations ritten acorJ~ai or disapproval of items considered under 6.5.1.6.(a) t~l"e1:1§~ (el

~.

(}.,.. /;

A~fiura.1Jc:e o../10/

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President and Chief Nuclear Officer and the General Manager - Nuclear Safety

~e¥iew of disagreement between the SORC and the General Manager -

Salem Operations; however, the General Manager - Salem Operations shall havekesponsibility for resolution of such disagreements pursuant ~o 6.1.l above.

RECORDs-<'.-IAtJO 2fPoR15\\

6.5.1.9 The Station Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President anc I Chief Nuclear Officer, the General Manager - Nuclear Safety Revim1 and tne Manager -~Off Site Reuiew.

A

_1 A__

_ _ 1 J

~tif ns5<tflMt:e a;'l(Y(

6. s. 2 NUCLEAR SAFETY REV! EW(

IANO AVOllJ FUNCTION 6.5.2.1 The Nuclear Safety Review Department tN-5-R+ shall function to provide the independent safety review program and audit-of designated activities.

COP~POSITION

§.§.2.2 NSR sRall eaAsist af tRe GeReFal MaAageF

• N~slear ~afety Revie11. :"e MaAageP OA Site Safety Revie\\4 Gl"e1:1~ (SRG), "14Ae is s1:1~~el"ted ey at 1east i~..

• aeaisatea, fijll-time eAgiAeePS leeatea SA site, aAa tRe MaAageP Off Sit~

~evim1 GPOij~ (OSR) WAG is s~~~oFtea ~y at least foijr aeaisatea, f~ll*ti~e eAgiAeeFs losatea eff=site.* TRe OS~ staff sRall

~assess ex~eFieRse a*a competeRse iR t~e geReral areas listed in Sectioa 6 S 2 4 The Ge 0 eril ~anagic ana MaRagers sRall

~etePmiAe 1~ReA aa~itieAal tee~Aieal ex~ePts s~o~l~ ass's:

iA PevieHS ef eem~lex ~l"eblems.

t Sinse the NijsleaF DepaFtment is loeatea on Artifisial Island site, tRe teFl!'IS "eA site 11 aAQ "off site" COA'ley tRe aistiRGti9R bet*.~een insiae aR~ o~tsi~e tRe statioR feAee, Pes~eetively.

SALEM - UNIT 2 6-9

~mendment No. 76

INSERT l TO SECTION 6.5.2 COMPOSITION 6.5.2.2 The Nuclear Safety Department, under the cognizance of the General Manager - Quality Assurance and Nuclear Safety, shall consist of the Manager - Nuclear Safety, the Offsite Safety Review staff (OSR) and the Onsite Safety Review Group (SRG).

The OSR staff and the SRG each consist of at least four dedicated, full-time engineers.

The Manager - Nuclear Safety and the Offsite Safety Review staff shall meet or exceed the qualifications described in Section 4.7 of ANS 3.1 - 1981 and shall be guided by the provisions tor independent review described in Section 4.3 ot ANSI Nl8.7 - 1976 (ANS 3. 2).

The Offsite Safety Review staff shall generally possess experience and competence in the areas listed in Section

6. 5. 2. 4. l.

A system o*f qualified reviewers from other technical organizations may be used to augment CSR staff expertise in the dis*ciplines of Section 6. 5. 2. 4.1, where appropriate.

Such qualified reviewers shall meet the same qualification requirements as the Offsite Safety Review Staff, and shall not

!lave been involved with performance ct tha original work.

The Onsite Safety Review Group staff shall meet or exceed the qualifications described in Section 4.4 of ANS 3.1 - 1981.

NSR sFial 1 blti 1 i ze a systeFR ef oual if~ ea l"evi e*.1eios f, el'!'I oti"le1 :e_:;.. _a.

eP§aRizatieRs te awgmeRt iti ix~ertise iR the diseieli~es ef See:'.eA 6.:.2. *.

Sl:ile~ ~blalifiea Peviewers shall ~eet the saFRe awalifieat~el'l PeabliPeffieAts as :r

'45R staff, al'ld Hill Aet AJ'o'e eeeA il'l"<telvea 11itl'l

~el"fe,.mal'lee of ti'le 01 :;i*1a

~

The MaAa~eP Qff Site ~eview aRd Staff shall FReet eP e*eeea the

~ualifieatieRs eeseri9ea iR SeetieR 4.7 ef A~~ l.1(1981) aRa shall ~e §u1ae~

~Y tl'le ~PevisioAs feP iRaeeeRaeRt Peview aesel"i~ea iA Section 4.3 of ANSI Nl0.7 (1976) (ANS 3.2). The Mal'lager 01'1 Site Review and staff will me@e 01 e*ceea the ~walifieatie"s aeserisea iR SeetieR 4.4 ef ANS J.l (1981).

CONSULTANTS 6.5.2.3 Consultants shall

a. Nuclear Power Plant Operations

b. Nuclear Engineering

c. Chemistry and Radiochemistry

d. Metallurgy

e. Instrumentation and Control

f. Radiological Safety

g. Mechanical Engineering

h. Electrical Engineering

i. Quality Assurance j.,Nondestructive Testing

k. Emergency Preparedness TFie OSR sFlall alse fblAetieA te eMamiAe ~laAt e~eFatiRg eharaeteristies, MRC issYaRees, iRablstFy adviseries, Lieel'lsee E~el'lt Reports, al'ld other setil"ees whieh FRay iRaieate areas fer im~reviRg ~laRt safety.

SALEM - UN IT 2 6-9a

... ~ndment No. 76

+~e Of; R ~~-Fr.

rlese* aiAoliu t;,-h0rl I eriC.OJ'J'/ft~6&:

'l

. STct REIJI:::..I

~FF 6.5.2.4"J' The OSR shall review:

The a................ vS°af ety r£va 1 uati ons for1'

~

~ vthanges to procedures, ill

b.

c.

e/.

h/.

equipment, or systems~and

-;!' vfests or exReriments completed under the provisions of Seet'si:i

.tS0.59, jlOCF_Vto verify that such actions did not constit~te an unreviewed safety question;

a;iJ fe<;f,~ e>i!" e;r;0e6111er1fs Proposed changes to procedures, equipment, or system hat involve an unreviewed safety question as defined in1

!etieR 50.59; jlOCF~A Pre~ese~ tests eF eK~eFi~eRts ti'lat iRvelve aR uM1 eoiewe~ safety

~uestieR as aefiRea iR SeetieA 50.59, 10CFR.

Proposed changes to Technical Specifications or to the Operating Licensej Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significancej Significant operating abnormalities or deviations from normal ana expected performance of plant equipment that affect nuclear iafet~

All REPORTABLE EVENTS; All recognized indications of an ~nanticipated deficiency.in some aspect of design or operation of safety*relate~ structures, sys:~ms or componentsj~t.a+ ct?u!O/ aFfuc.f-11µcfear Stck~j Reports and meeting minutes of the Station Operations Review Committee.

AUDITS 3

~ka1/I 6.5.2.4J" Audits of facility activities ti'lat al"e l'ef:lblil"eEi ta' be performed under the cognizance o~",QSR at'e 1 i steEi ae le*.~:

a, The conformance of facility operation to provisions contained within the Technical Specifications and applicable l~cense conditions at least once per 12 months.

b.

The performance, training, and qualifications of the entire faci'.':;

staff at least once per 12 months.

c.

The results of actions taken to correct deficiencies occurring in facility equip~ent, structures, systems, or method of operation t~a:

affect nuclear safety at least once per 6 months.

d.

The performance of activities required Assurance Program to meet the Criteria least once per 24 months.

SALEM - UNIT 2 6-10 by the Opera~~al Quali:;

of Appendix C18 d"flOCFRSO, a:

lE1 Amendment No. 76

AUDITS (continued)

e.

The Facility Emerge~cy Plan ana implementing procedures at '.:as:

once per 12 months.

f.

The Facility Security Plan and implementing procedures at least Jnce per 12 months.

1 1

(i...0.1; Assura11c'e _a(l(J(

g.

Any other area of facility operation considered appropriate by the General Manager - Nuclear Safety Review or the Vice President and Chief *.uclear Officer.

h.

The Facility Fire Protection Program and implementing procedures at least once per 24 months.

The

i.

AR iRele~eReleR"Mire protection and loss prevention program r:::i iRs@eetieR aRel a~elit sAall ee ~erfeP~ea at least once per 12 mon~ns

~ utilizing eitheriqualified offsite licensee ~eFSQRRel or an outsice I iflclepe11ckY1f]

) fire protection f:rc prv ctiot1 enerineer&)

n-./

GOfl SIA /+11t'I f v

l::!..:l An tt 0

ttn;~~*'-1-A-e--~~.....-lil+-~l-'l~*-l~~~+Qol~l-R-lil,_._Q.§.!s--;;M=-e~~~

I sh111/ ~e u+;hreJ ~+I outside fire~onsultant ~

nolepe11rle11f pro fee f;"~

j )(.

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

pla.t1f. 111t(IJ The above audits ~e conducted by the Ni:iel ea!" Qua 1 i ty Assurance Firv:tf a.iAd;t

• Department or an ind'ependent consultant.aa requiFed. Audit Pes1o1lts aREI ref!Dr+5 1--~~~lefl'~ir*foeof'l'fr sha 11 be reviewed by"'9'91t.

1.-.s: <.!;'j

>ON-S !TE SAFETY REVIEW ~7at~: :lj ;R..j 9-+-1.e-o-~-R-s-to.-f"'.".:f:-Tj

..------~}

f.il I

FVNC.TION j 6.5.2.St"'The On-Site Safety Review Group (SRG) sh~ll function to provide: the review of plant design and operating experience for potential opportunities ~o improve plant safety; the evaluation of plant operations and maintenance activities; and advice to management on the overall quality and safety of plant operations.

The SRG shall make recolTITlendations for revised procedures, equipment

. modifications, or other means of improving plant safety to appropriate station/ corporate management.

RES PONS IBI LITI ES

~

6.5.2.5~ The SRG shall be responsible for:

a.

Review of selected plant operating characteristics, NRC issuances, industry advisories, and other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety.

b.. Review of selected facility features, equipment, and systems.

SALEM - UNIT 2 6-11 Amendment No. 76

INSERT 2 TO SECTION 6.5.2 RECORQS AND REPORTS 6.5.2.4.4 Records of OSR activities shall be maintained.

Reports of reviews and audits shall be prepared and distributed as indicated below:

a.

The results of reviews performed pursuant to Section 6.5.2.4.2 shall be reported to the Vice President and Chief Nuclear Officer at least monthly.

b.

Audit reports prepared pursuant to Section 6.5.2.4.3 shall be forwarded by the auditing organization to the Vice President and Chief Nuclear Officer and to the management positions responsible for the areas audited (1) within 30 days after completion of the audit for those audits conducted by the Quality Assurance Department, and (2) within 60 days after completion of the audit for those audits conducted by an independent consultant.

RESPONSI8ILI;~ES (continued)

c.

Review of selected procedures and plant activities inc~uaing maintenance, modification, operational problems, and operationa:

analysis.

d.

Surveillance of selected plant operations and maintenance activit~es to provide independent verification* that they are performed correctly and that human errors are reduced to as low as reasonably achievable.

NSR AUTHORITY 6.5.2.6 ~

hall report to and advise the Vice President and Chief Nuclear Officer on those areas of responsibility specified in Sections 6.5.2.4 ana

6. 5.2. 5.

6.5.2.7 Reeerels ef NS~ aetivities s~all ee ~Fe~aFe~ aR~ maiRtaiRe~. Re~eFts ef rev i e~1s a rut a1:1el its sl'la 11 ee el i str i e1:1tea as f e 11 e*,,s:

a.

e.

6.5.3

~re~aFeel, a~~Feve~ aRa feFwaFae~ te t~e Viee PFesiaeRt aRel C~ief NbleleaF GffieeF, witt!liR 1q aays felleHiRg eem19letieF1 ef tf'le reo*ie...

Aijelit Fe99Ft5 eReempasse~ ey SeetieA 6.S.2.q,2 aeeve, sl'lall ee fer*11arelea te tPle Vi ee Presi Eieflt al'lel CP!i ef N1::1el ear Offi ee1 and to tJote j maRagemeRt ?Q&itieRs FeS?QR&ible feF tRe aFeas ablaitea witt!liR JQ elays afteF eempletieR ef tRe await.

TECHNICAL REVIEW ANO CONTROL ACTIVITIES 6.5.3.1 Programs required by Technical Specification 6.8 and other procedures which affect nuclear safety as determined by the General Manager - Salem Operations, other than editorial or typographical changes shall be reviewed as fa 11 ows:

PROCEDURE RELATED DOCUMENTS 6.5.3.i Procedures, Program and changes thereto shall be reviewed as follows:

a.

Each newly created procedure, program or change thereto shall be independently reviewed by an individual knowledgeable in the subject area other than the individual who prepared the procedure, program or procedure change, but who may be from the same organization as the individual/group which prepared the procedure or procedure change. Procedures other than Station Administrative procedures wi1~

be approved by the appropriate Station Department Manager or by t~e AssistaRt General Manager - Salem Operations. Each Station Department Manager shall be responsible for a predesignated class Jf procedures. The Genera 1 Manager - Sa 1.em Opera ti ans sha 11 approve Station Administrative Procedures, Security Plan implementing procedures and Emergency Plan implementing procedures.

• Not responsible for sign-off function SALEM - UNIT 2 6-12 Amendment No. 76

PQOCEDURE RELAT~D DOCUMENTS (continuea)

b.

On-the-spot changes to orocedures which clearly do

~ot c~arge :Re intent of the approved procedures shall be approved by two memoe~s of the.plant management staff, at least one of whom hoids a Senior React~r Operator License. Revisions to procedures which may invoive a change in intent of the approved procedures, shall be reviewea i~

accordance with Section 6.5.3.2.a. above.

c.

Individuals responsible for reviews performed in accordance with item 6.5.3.2a above shall be approved by the SORC Chairman and designated as Station Qualifjed Reviewers. A system of Station Qualified Reviewers, each of whom shall possess qualifications that meet or exceed the requirements of Section 4.4 of ANSI Nl8.l - 1971.

shall be maintained by the SORC Chairman. Each review shall include a written determination of whether or not additional cross-disciplinary review is necessary. If deemed necessary, such review shall be performed by the appropriate designated review personnel.

l+i.e OS~ ~to.FF'j

d.

If the Department Manager determine that the documents involved rri_e_o_<<_i r-e-.....

--,0

-c._F_R_S1_~.-5"t:t-,..~;...

• the doc um en ts s r :: 1 1 be fo rwa r ct e d o

for SORC review and also to ~for an independent ~eview to St:tfefy e?.ll'tlt.laf*r>f'I determine whether or not an unreviewed safety question is involved, Pursuant to 10CFR50.59, NRC approval of items involving unreviewed safety questions or Technical Specification changes shall be obtained prior to implementation.

NON-PROCEDURE RELATED DOCUMENTS 6.5.3.3 Tests or experiments, changes to Technical Specifications, and changes to equipment or systems shall be forwarded for SORC review and also to

.-----,~---)~NSR-for an independent review to determine whether or not an unreviewed safety uestion is involved. The results of.

reviews will be provided to SORC.

Recommendations for approval are made by SORC to the Gener~l Manager - Salem

• Operations. Pursuant to 10CFR50.59, NRC.approval of items involving unreviewed safety questions or requiring Technical Specification changes shall be obtained prior to implementation.

. RECORosM AND REfoRTS I 6.5.3.~ Written records of reviews performed in accordance with itrrle 6.5.3.Za above, including reco11111endations for approval or disapproval, shalf"'be maintained. 'Copies shall be provided to the General Manager - Salem Operations, SORC, F and/or NRC as necessary when their reviews are requirea.

6.6 REPORTABLE EVENT ACTION 6.6.l The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and/or a report submitted pursuar:

to the requirements of Section 50.73 to 10CFR Part 50, and

b.

Each REPORTABLE EVENT shall be reviewed by the SORC and the resultant Licensee Event Report submitted to nd the Vice President and Chief Nuclear Officer.

+lie OSI!. sft..FF SALEM - UNIT 2 6-12a Amendment No. 76

6.7 SAFE7Y LIMIT VIOLAT:CN 6.7.1 The ;ollowing actions shall be taken in the event a Saf~ty -*~*: 's violated:

a.

The unit shall be placed in at least HOT STANDBY within one hour.

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President and Chief Nuclear Officer and General Manager - Nuclear Safety ~ 11ie*t1 shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Q.-/d 4 6'1,rruice a.Y1o/

c.

A Safety Limit Violation Repcrt shall be prepared. The report shall be reviewed by the SORC. This report shall describe (1) applicaole circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to tne Commission, the General Manager -

uclear Safety R-eview and the Vice President and Chief Nuclear Offic r within 14 days of the violation.

Q,µ:.. f i +y Asf u f'Q.(lce a viA SALEM - UNIT 2 6-12b Amendment No.75

• At~lNISTRAT!VE CONTROLS s.. 8 PROCEDURES AHO PROGRAMS s.a~ 1 Written pi'"oc.dUres shall be establ t sh*d, i""21 *mnted and *rna1 ntai ned covering the aet1v1t1es referenced below:

a *.. ~The !pp11cab1e procedures recol!l!!!nded 1n Appendh *A* 11f. R,'!9Ul a~ry Guide 1.33. Revtston z *. Feb.-uary 1978.

b.

Refueling operations-.

c.

Sur'19111anca and ust act1.vttiu of. safety related equ1pmnt.

d.

5eCUf'1ty Plart 1mp11mmntattan.

~91nc1 Pl an 1mpl~mntat1on

• Ftre Protact1on ~gr111 f111Pl1m1ntat1on.

PROCESS CONTROL PROGRAM tmplemntat1on.

g *.

tr.

OFFSITE DOSE CALCULATtON MANUAL 1mpleNntat1an.

t.. ~a11ty Assurance Progra* ro.. effluent Ind envtro,..ntal mnf tor1 ng.

6.8.Z

• Eadt procadUre and adnrtnistrath* pol tcy of 6.8.l" aba'le.. and c:han99s.

ther*ta. shal 1 be revt.-d and approved in accardanc. wttb Spec1f1at1on 5.5.1.6 I or 5.5.3. as appropriate. prior tO tmplemntatton and reviewed pec-todi"cally as set forttt tn adll1ntstrat1ve proc.dures.

-6.8.3 On*the-sPJt dtan99s to proc.dures of 6.8.1 abave* may be made* pt;"ovtd*d:

a.

b.

c.

The tntent* of tn* original pracadW"t ts nat altered.

The change ts IJlproved by em nambers of th* pl ant manag*1111nt staff, at least one of wham holds a Senior Reactor Operator's l.teense on the unt t affected.

The dtan99 1-s d2cu*ntld and r9ceiv*s the saa. level of reyfew and approval as ttte artginal procedure under Spectftcatton 6.S.3.2a witnin 14 days af t""'lemntatton.

SALEM

• UN IT Z 6-13 Amendment No. 33

f i

ACMIMISTRATtVE co~~OLS s.a.4 Th* folla.1ng programs shalt b* 1111tnt11ned:

1.

P~illll!"Y C4al1nt Saurc1s Outside Cantafnlll9nt A pragr*~ta rtduc1 1 ukage fr"QI thas. partf ons of systlllS auts1d1 canta111Mf'1~ tftat. cauld cantijn highly rad1aaa1ve f1ufds during 1 sari aus tr1nsf Int or 1cc:fdlftt ta u 1 aw n praaf cal 11vel s. The syst-fnclud1 (rte1rcuht1an spray, nfety 1nJtct1an, cnafcal and vol um ca~trol, gu stt1pper, rteambfn1~ **** ). Tiie pragr* sha1 r 1ng1uda tile fa11a.1ng:

(1),,...,tntath* *1ntanan~ and periodic visual 1nspact1an requ1~!9

"*"* uct (11)

Intagrattd ltak t.~ r.quirt1D1nts far Heft sy~* l't r1fuel1ng cycle 1nttrYals or ltils.

In-Plant Ra~1at1an Man1tar1nt A program *h1dl w111 wssure th~ capab111~ ta 1e.cur1t1.ly d1t1t'lllin1 the atl"bof"ft* 1od1n* conc1ntr1t1an 1n artu undlt" 1cc:ident cand1tions.

T!l1s progrl8 sna11 tnclude tft* fa11a.1ng:

(1) Tratn1nt ~f personnel,

( 11) Pl"GCadurH far raant tar1 ng, ll'id (111)

Pl"Ov1s1ons tar 1111fntan1nca of S11111111ng and analysis 1quti:=ent.

c.. -

Secondary Wat1r C!tilista _

A p~ram fa,. 1111111tar1nt of secondary "'tar dl*htry ta fnhibit stHll g*era~ar tube dqradation. ihis pragr1111 snall tnclude: *

(i} Idant1f1e&tfon at a s111Pling scn1dut1 far the critical variables lnO tft* '°"tro\\ pairtis far tft11* vat11bl1s, (11) tdeni1f1cat1on of ttt* pracKurts used to mauur* tft* YtluH af tM* ct1"t1al Yari&bles, (ii1) Identification of ~rcc1ss SIJllP11ng paints, 1nclud1ng man1tar1ng at tn1 41sdlarge of tft* cand1nsat1 ~umps far t¥1dtnc1 of candtnsar in*l etk*g*.

(iv)

Pl"Octdur-es far th* Mt<ord1ng and management of data, (Y) *Pf"Octdur-es defining c~rrec-:1ve actions for off-contra1-~a1nt cne111stry conditions.

(vi)

A ~racadu.-. 1dentH'y1nq (a) tne autnarfty !"9s~ansible for tn*

1nt1r~ret1tton of tne data. and (b) tne sequence and tfm1Mg of adlll1nistrattve 1vents 1'"9quf red to fn1tfat1 corrective *action.

SALEM

• UNIT Z S*l4

• Amandment No.* 29

ADMINISTRATIVE CONTROLS

d. Backup Method for Determining Subcooling Margin A program which wi 11 ensure the capab11 ity to accurately monitor the Reactor Coolant System Subcooling Margin.

This program shall include the following:

( i )..

1 Training of pe~sonnel, and I

(11) Procedures for monitoring

e. Postaccident Sarrpling A program* which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment*

atmosphere samples under accident conditions. The program shall incl~de the following:

(i)

Training* of personnel (ii)

Procedures for.Sa1!1Jling*and analysis, (1"11)

Provisiona for maintenance of sa111>ling and analysis equipment* *

• -It is acceptable if the licensee maintains details of the program in plant operation manuals.

SALEM - UNIT 2 6-14a Amendment* No*. 42 I

J ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE R~PORTS ANB REP9RTABLE 9CCURREhES 6.9.l In addition to the applicable reporting requirements of Title 10 Code of Federal Re ulations, the following reports shall be submitted to the dministrator

~r&e~t-eR-aiM--e-ft'F-Etfle@RHM:t:&- un 1 es s at he rwi s e noted

• STARTUP REPORT v.s. Nv' lettr.eeljcila-fory Commi s-s l01t11 Ooeurl'let1f t:c.ritn,./

Oes111, WAshill~fr:,.,, o.c.. "JOS56; c..Jif~ 0.. COfy ~ 1k ustJec.

6e9.l.l A summary report of plant startup and power escalation testing shall be submitted following {l) receipt of an operating license, (2) amendment to the license involving. a planned increase in power level, {3) installation of fuel that has different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, Qr hydraulic performance of the plant.

6.9.1.-2 The startup report shall address each of the*tests identified in the FSAR and shall include a description of measured values of the operating conditions or characteristics obtained during the test program and a comparison af these values with design prediction$ and specifications. Any corrective actions that were required to obtain* satisfactory operation shall also be described.

Any addf ti onal specf fi c details requf red in 1i cense conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shal 1. be. sub111itted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or conmencement of *commercial power operation,.pr (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or com111encement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed *.

ANNUAL REPORT~~

6.9~1.4 Annual reports covering the activities of the unit as de*scribed below for the previous calendar year shall be submitted prior to March 1 of each year. TRe iRitial FepeFt &Rall ee SYemitted pFieF te MaPeR 1 af the yeaP fellewiAg iAitial ePi t_i eal1 ~,

-~d= A single submittal may be made for a multiple unit station.

• The submittal should combine those sections that are common to all units at the station.

SALEM - UN IT 2 6-15

AOM!N!STRAT!VE CONTROLS 6.9.l.5 Reports requ1rtd on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, ut111ty and

-f/ierrro lu.111,"ne~f c( f>§; 17ff.fe r other personnel (including contractors) receiving exposures greater than 100 mren/yr and the1 ~ assaci ated man rea exposure accord1 ng co woiMl and job f.unct1ons~.g., reactor operation~ and surveillance, inserv1c1 inspection, routine maintenanc1 1 special maintenance (describe 11111nt1nance),._,.ste processing, and refueling.

The dose usi nment ta various duty functions may be estimates base<1 on pocxet dos met1r 0 or measurements.

Small ;xposures totalling less than 2 o t

• 1nd1v1du1l total dost need not be accounttd for.

In th* agg,..g1t1, at 111st soi of th* total whale body dost received fr"(9 e~t1rn1l sources shall be assigned to sp.c1fic major we~

funct 1 ans.

b.

The ~1tt1 results of steua generatQr tube 1nservic1 i.nspections performed during th* report per1od (r1ferenc1 Sp1c1f1cat1on 4.4.5.5.b).

MONTHLY OPERATING REPORT 6.9.l.5 Rout1ne reports of operating statistics and shutdo*n experience, including documentation of all challenges to the PORVs or safety valves, shall be submittld on a monthly basis to the~,....~,.,. -G-f~~~~~~~~~~~;_J t1en and P~9ra11 Aft1lys1s, U.S. Nuclear Regulatory Commission, 20555, with a copy

, no later than each month foll a.1 ng th* caltndir month covered the re art.

~EPORTABLE QCCUAAEMCES To +lie USftJeL Aol.,;nis~fbr, r2 iol\\ I s,9,1,7 Tite AEPQATABLi QGCUAAEMGES ef Spec1f1cat1ens S.9.l.8 aftd Sa9al19 eel~.

1111111ti1 "9 ESfPt"'leth* idf CftS ind musiires to "'"'"e rectsrrenee, sr.11 l be repal!"'tl4 t; tn1 NAC, sij,,1...,.111 re,o.-es may be rl!(!~ired te f~11y descr;ee

• f1Ril

~salij;1eft ef oeeurrtfte1.

tft e:aJe ef eorrected or supplemeftta~ reDerts, a H censet ue,,t report shill be eom,1 ned a*,.d referel"IH slilall Bt 111aie u tAe a.. 1 !1 ftil """ dau. *

?ROMPT NGT!F!CAT!ON W!l11 WR ITT'EM FOL!:SWl:IP s.;.1.a

~e ty'*s af e¥eft15 l1st1e Belew sn111 Qe repe,.iee ~itAiA 24 Aawrs ;y t1l1;AaA1 iAt 1aftf1fl'llei llYJ c1l19rap~, 1111119,.1111, er faeS111111 trafts*1ss1eft ta tRe

~'111111111tr1t;F af ;he R191;n1l Qff1;1, aF Ail ~1cign1t1 AG 11:1r==*n==* firs:

~l"lt1"9 day foll~;,.g tl'le 111nt, Mith 1 wr1tUn fe11~~P repcl"'t wit1'11,. H days.

O,e 11dl!"'tUA f;ll°""'ll ~llQFt IAill 1111clwGe, HI ISCAi111Wll1 I Gallltle,eG HllY Elf i l tcensee ewe,,t 1 eDOl"t form.

Infel"llll'ti=in l'rov1ded en tl'le l 1ce,.see *..,,,.,,.e,el"t

• f;"" sn1ll Bt swppl1111tftted, as "'!tdeQ 1 Qy 1tG1t1anil 1111rr1t1v1 =1t1ri1l t; llPG\\'ide ea11tt9leu u111ta,.atieft of el'le etre1;11MUfteu sti1rret1ft811'1! tAe evefl!Co *

~ffiis taculation supplements the rtquirements of section 20.~07 of' 10 C~~

?art 20.

SAL~M - Ul't IT Z Amendment No. 28

INSERT TO SECTION 5.9.l.5

c.

The results of any specific activity analyses in which th* primary coolant exceeded the limits of Specification J.4.8.

The following information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while the limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit.

Each result should include date and ti.ma of sampling and the radioiodina concentrations; (J) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcurie* per gram as a function of time for the duration of the specific activity above the steady state level; and (5) Th~ time duration when th* specific activity of the primary coolant exceeded the radioiodin* limit.

AOMIMIS~T!VE CON~OLS

1.

F111 i,re of th* rueta,. prot1ct1 on syst* or oth1r sysums subject 11111t1ng s1f1ty syst.. sittings ta 1n1t11t1 th1,..qu1rtd prot1ct1 1 function by th1 t11111 a monitartd 121rU11t1r rHei!IS th* setpoint 01c1-f11d u

~* 11arft1ng 11f1ty syst* sitting 1n tl'I* t1chn1cal s c1 f1ca-t1ans or failure to c*llta tl'le.-.qui rtd prot1c:1v1 funct1 o

• Operation of th* un1t or 1ffectld systl!llS when any par er or 001r1-Qi'i siibject ta 1 11111ting ccnd1t1on fo,. oi:ierat1an 1s 1 s canurva-t than.the l11st cans1r"V1t1ve aspect af tht 11stt1 cand1t1on for

~ t1on.atl011sh8d 1n tl'I* tlChrrtal spec1f1cation *

c.

cmgr1d1t1on. d1scovertd 1n tuel cladding, 11cta,. ccal1nt boundary, or pr1*"1 conu1nmnt.

• d.

011111u 1nvah1ng d1s1grt..nt th the pred1cttd value

f.

of rtlC:i vi ba hnca und1r st11dy stat* cc c:ti*ti ons dur1 ng pa.er operation grt 1r thM or equal ta lS d1l k/1q a atcuhtld ruc-t1v1ey ba11nc1 d1ating 1 SHUTDOWll IN less c:ot1HMat1v1 tl'l1n specif11d 1n the achnial spec1f1ati s; shor:-tt,.,. ructiv1ty

• 1 nCl'HHS that cc pond to a r11ct iJ*r1 Cid af 1 ess than S seconds or, 1f su0cr1tic1l, unplanned

~1v1ty 1ns.r:1a. of llOl"'I thin

. O.!S d1lt1 kl'; or oc rrea of unplann8d c:r1t1a11ey.

F111urw er 1111funct1on could PrtYlftt, by 1tsel 1',

.ms of syst*( s) used to amrt ~on1nts wtt1 di pr.vents or fulfillment of the funct1on1l,..qu1r"9*

P* wt tl'I ICC1 dints lftl 1 y zed 1 n tl'I* SAA *

9.

Conditions ar1s1n f!"m natural or n.-ad1 events tl'11t, as 1 d1 rte?

.!"Uult of Chi 1

.-.quil"t un1t shut

, operation of uflty syst-, or r prauct1¥* *Hurts uirtd by tadln1cal spec11'1 at1

h.

Er,-,," d1 ftrtd 1n the transient or acc1d t 1n1lysn or 1n th*

mthacts sad for sudl 1n1lyses u dlscr'f bed tl'I* s*feey 1n1lys1s

~o~ r 1n the blsn for the tldln1cal soec1 i cat1 ans th&t nave or ccut hive p1,.,.1t*:ea rHC-:or operation 1n 1 man r iess ccnserv1t1v1 usumd 1n en. 1n1 lyses.

1.

erformana of siruciu,..s, systlftlS, or c~anents tH t r1qu1rts rtlllld1&1 action or ccr~'t1v* 1111sua-.s to pr.ven~ 001 t1on 1n 1 manner 11ss cans*rvat1ve th&n &ssUlllld 1n th* 1ccid1nt a 11ys1s 1n the safeiy an1lys1s*l"t1'al""t or eacnnical soecif1cat1ons basis, or d1scovtljl during un1t 11f1 of cand1tions nat soac1f1ca11y consid1 1n the safety anaiysis.-.oal""t or tachn1cal soec1f1cat1ons that~ 1rt rtlllld11l ac't1on o,. co,.~~~1ve measures to ~M!vent the ex1s'ta a or development of an unsafe cond1t1on.

j.

Offs1tt r"'lhas1s of. rad1oa~1v1 mattr1als 1n 11~uid and gueous e ~1 'J-ines tl"llt excaed tl'I* limits of Si:iac1f1cat1on 3.ll.l.* l or 3.ll.Z.l.

SAl.[.11

• UNIT Z 5-17 Amendmant No. ZS

/

CONTROLS S.9.1.9 Th* typ*s o 1v*nts 11stld b*law shall b* th* subjec of written reports ta th* Adm1n1s rator of th* R1g1ona1 Off1c1 w1th1n 1rty days of occurrenc* of th* 1vent. Th* written nport shall includ* 1s 1 ra1n1mwn, a c~lettd copy of 1 11c1n 11 1v1nt MIPOrt fal"'lll.

Info~ on provided on the 1ic1nsee 1vent report fol"'lll hall IM suppl11111nttd, 1s ne ed, by 1dd1tianal n1rr1t1v* 111t1r1*1 to prov1

~l*t* axpl1n1t1on of

• c1rcU111stances surround1ng the 1vent.

a.

Re1ctor prot1ct1on sys m or 1ng1nffrwd af1ty flatun instrument sittings which are foun ta b9 11ss '° 1rvativ1 than thos1 estab-1 ishtd by th* technical ec1f1cat1o but which do not prev1nt the fulfillment of th* functio 1 requi nts of affected systems.

b.

a degraded mad* perm1tttd by a or plant shutdown required by a

c.

ntat1on of adm1n1strativt or cause reduction of de9r99 of on systems or en91n1ered safety

d.

Abno~l d1gr1dlt1 of systems oth*r tha thos* sp*cif1td.in S.-9.1 :a.c abov* d i gntd ta '°nta1 n rad1 oa h1 iut1r1 al resulting fra1 th* f1ss1on pl"Qc1ss.

a.

of 1) mare than l uri

• of rad1 oac~ he mat1r11l 1n 1quid 1fflu*nts, 2) rnare than 150 cu 1es of noble gas in g&SIQ\\IS 1f u9nts. Th* report of an unolann~ off ite release of rad10lct1 1 mat1r1a1 shill 1nclud* the folla.ing 1n rm1t1on.

l.

and 1qu1 pm*nt rel HSI.

Actions taken to prev1nt recurrence.

Consequences of the unplanned release

• Iii I I /sAl.S:M - UM IT 2 s;.. La Amendment No. za

.1./

I

---*----------------------------------**J

AOMIMISTitAT!VE CONTitOLS AICNUAL RADIOLOGICAL EMVIROMMENTAL OPEAATIMG REPORT*

I!} 5.9.l::if Raui1ne R1d1alo.g1c1l Envir""Omnental Operating Reports covering tht

~ 1rat1on of th* ww1t during tnt previous c:iltncar y11r shall oe suomitted pr1or ta MIY 1 of Hct'I yeir.

Th& Annual Rad1olog1c:il Env11""0n1111nt1l Operating R'lports shall include summaries, int1"'ret1t1ons, and an analysis of t~nds of the l"tSults of th* radialog1cal en'firanmntal sunt1111ne1 1ct1v1t1es for th* l"tport period, -including a eClli*

p1r1son *1th PC'IOP*r1t1anal studies with ~1r1t1anal centrals (1s appropr1ata),

and w1 th prev1 ous tnv1 ranmntll su,..,.111ne1 l"tPQrts, and an ass.ssmnt of the aasentd 1111111cu of th* plant °"erat1on on th* 1nv1~nt. Th* l"tports shall alsa include the l"tSults of land use ctnsus.s.-.quired by Spec1f1cat1on 3.12.z.

The Annual Rad1o1QCJ1cal Enyiron11ent1l Operating Rttiorts shall include th*

l"tsults of analysis of all r1d1oloqtca1 en'fironmnul s*l*s and of 111 meu-ur..,.ts tllctn dur1"9 th* 129r1od pursuant ta tne Table and Figures in tht 1t1v1*

l"OftmftUl rad1at1on stct1on of th* OOOI; as.. n u s~r1Zld and Ubuhttd re-sults of locations spec1f1td 1n these analyses and muu.-...nis in the format of the table in th* Rad1olog1c:il Asses~ Brandl Technical P~1t1on, Rtv1sfon 1, Novai:ler 1979.

tn the t¥ent that Semi 1nd1v1dual l"tSults are net 1v11hl:llt for inclusion w1 tn the l"tt'Ol°"t, the l"t1'0rt shall be subst tttd not1 ng 4nd uph i ni ng

---

the l"tHons for th* missing l"tsulu. Th* llfss1nt diia snall be sul:lll1tttd as soan as possible fn a suppl.-.nta~ ~M:.

o*~,,..,.,.,*r., ~

!.'11.*"~I.-"' 1-.J.i*,,..; The l"t1'0rts shall also 1nclua thw fo11awing:

a sumtry ctascr1pt1on of the r.11a.r *+'t, Si~

rad1a1QCJ1ca1 tn'f1ranmenta1 witoring pragrm; at lust two l*g1blt 1111ps-.....,..

oOV1JOl+~Y**~

~IP"l"'f Ill U11Pl11tg locai~o111 k11ed ta I Utile ftving d1stancu and d11"tct1ons SQ fie(

f,.,. the c.nt1rl1n* of one l"'HC:ar; tht,,sults af 11cansH p1rUcil)1t1on 1n the A

Go

-rli Intmrl 1aoratary capri son Pl"'Qtr*. requ1 red by S~ec1,, cat1 on 3.1z.1; and dis*

'overi11~

e cuss1an of 111 analy'a 1n _..1ct'I the~,..quired o, T1bl1 4.1%*1 wu not

'1'tore. ;/t:,-hu1T 1Cl'l11v1b 11 *

... '_._'"-~-~_

• . _,,_4_,_, __ SD4IAltNUAL RAOtOACTtV! Em.uw RELWi REPORT*

5.9.l.4( Ravt1nt Rad1oac:1ve Ef1'1uent Ral11s* Re"°rts caver1ng tl'le operat1on of tl'le un1t clllr1ng the pre.,1ous six mnths of ~1r1t1on shall 01 sut:lllitted within 50 u11 attar Jan~~ 1 and July 1 of 11ct'I year.

Th* R1d1oact1v1 Ef1'1uent R1l1as1 Re"°rts shall 1nc1uda 1 s~~ of tl'I* ~uant1-t1es of rad1oact1v* 11qu1d and gaseous 111'1uents and sa11d *Htl l"tltutd froan tl'la un1t 1s outlined 1n Rt9'1l1tary Gu1dt 1.%1.

• f11t1sur1ng, Ev1lu1iing 1 and

• A single sue11itt1l 1111y be 1111d1 far 1 1111ltipl1 ws1t station.

The submittal should c=-tline tl'los1 sections that ll"t ccaman ta all units at the station;

~°"ever, for units with s1p1r1t1 r-ac:r..1st1 syitllllS, tl'lt submittal sl'lall s"1c1fy tn1 l"tltas*s of radio1c-:iv1 1111t1ri1l f~ 11ct'I unit.

-tn 11et1 ef 9tti*1Uhft *1tft,... ~....... 1 il1a11la91Hl 6ft*g1~ftllllftCll Q.. P'H11'1!

il111.... \\i.t l i....... l!IH ;a, ;11c1 ;,. ;f r9(1 l i=ii i=ig ':Ai I IWllDU'Y ;f r9qw i =w

• He,.ele91e*1 dtH en 91!1 1n 1 file ei.1t !l'l11l 9* ~,.e,i~*d *e '" MRG ~H" l"~Utl;,

SALiM

• UNIT 2 5-19

ADMINISTRATIVE CONTROLS

---

~--------------------------------------------

Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Po.,.er Plant,,, j'.S]

Revision l, June 1974, with data surnnarized on a quarterly basis following the format of Appendix B thereof.

The Radioactive Effluent Release Report to be submitted within 60 days after January l of each year shall include an annual summary of hourly meteorological data collected over the previous year.

This annual sul'll'lary may be either in the form of an hour-by-nour 1 isting of magnetic tape of wind speed, wind direction, atimspheric stability, and precipitatilln (if ITl!asured), or in the form of joint frequency distributions of wind speed, wind direction, and atimspheric stability.~Th1s same report shall include an assesslTl!nt of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

Th1s same report shall also include an assesslTl!nt of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PIJBLIC due to their act1v1ties inside the SITE BOUNDARY (Figure S.l-3) during the report period.

All assu~tions used in l"aking t~ese assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorolo.gical conditions concurT"ent with the time of T"elease of radioactive materials in gaseous effluents (as determined by sa~ling frequency and measurement) shall be used for deter~ining the gaseous pathway doses.

The assesslTl!nt of rad1atiof'I doses shal 1 be performed in accordance with the OFFSITE DOSE CALCULATION.MANUAL.

The Radioactive Effluent Release Report to be submitted 60 days after January l of each year shall also include an asse5'5ment of radiation d:lses to the likely rrost exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and d1rect radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Rad1at1on Protectilln Standards for Nuclear Fower Operation.

Acceptable ~thods for calculating the dose contribution from liquid and gaseous*

effluents are given in Regulatory Guide l.l09, Rev. l, October 1977.

Thi! Radioactive Effluent Release Reports shall include the following infC'lrl'latign for l!ach class _of solid waste (as defined by 10 if Part 61) shipped offsite during the report period:

a.

Container wlume,

b.

Total curie quantity (specify whether determined by "1!asurement or estimate),

c.

Principal rad1onuc11des (specify whether determined by measurell't!nt or estimate),

d.

Source of waste and processing e~loyed (e.g., dewatered spent resin, co~acted dry waste, evaporator bottoms),

• flfn lieu of submission with the first half year Radioactive Effluent Release Report, the licensee has tl'!e option of retaining this summary of required l"l!teorolog1cal data on site in a file that shall be provided to the NRC upon request.

SALEM

• UNIT 2 6-20 Amendment*No. 36

ACMINISiRATIVE CON~OLS

1.

Type of cont11n1r (1.g., ~SA. Type A, Type B, ~1rg1 Qu1nt1ty), and

f.

Sol1d1f1cat1on agent or absorbent (1.g., Clftl9nt, urea fo~ld'if,yde).

Th1 Rad1oact1ve Effluent R1l11s1 Reports shall 1nclud1 1 list of d1scr1pt1o~f unplanned rel11s1s frQI tJ'I* s1t1 ta UNRESTRICTiD AREAS of rad101c-t1v1 rn1tar1ats 1n pseaus and 11qu1d effluents rude (!.ur1ng th* repor-t1ng p11"1od.

Th* Rad1oae't1ve Effluent R1l11s1 Reports shall 1nclud1 1f1Y d'l1ng1s 1111d1 during the reporting ~er1od to the PROCESS CCNTROL PROGRAM (PCP) and to the OFFSIT'E DOSE CALOJLATtOM MAHUM. (OQCM), u.. 11 u 1 11st1ng af nw locations far dose calcul1t1ons and/or env1rGftllllfttal man1tor1ng tdlnt1f1ed by the land use census pu1"1u&nt ta Spec:1f1cat1an 3.12.2.

11 SE:E JAJse.llT,....

U.S. Ni,cdpqr-e~" << r'I

..,.,,,;s~;~,,,

SPECt.AL REPORTS J

i:Ax.u.-rtti'rr+ 9-;.fro/ ()rs~, iJa.sl. 0'nj"iori O.c.., -;0555, v;ft, ~ <.:.e>>/Jy -h> +lie 5.9.2 Spec:1a1 reports shall be subll1tttd to the Adllin1stratori 9ff111 w1th1n the t1* period specified far 11ch repart;:.:.*~-__.--=--~

I 1 l)SrJRC R:~jon r I S.10 RECORO RET!MTtON In add1t1an to the 1ppl1cabl1 record retention requ1renents of Title 10, Cod* of Ftd1r1l R1gulat1ons, th* fallowing records shall be re~ned for at least tilt nrin1-p11"1od 1nd1catld.

/o.'

s.10.1 The fallawtng r.caf'ds shall be retained for at 111st f1v* y11r':

ti.

c.

Records and logs of unit op1r1t1an covering t1N interval at Hd'I power level.

Records and logs of pr1nc1p1l 1111nt1n1nc* act1v1t11s, 1nspect1ons, nt:i*1r and repllc-nt af pf'1ncipal 1t.. of equ1?111nt rehttd to nucll~f' Slfltyj EVENT.SJ

• ' REPORTA8USeS4RREM£!5 submitted to tilt C~1ss1on.

d.

Records af surve1111nc:a. IC't1v1t11s, 1nsptct1ons and ca11brat1ons

[ DE"LEl.e:OI requ1 red ay tl'la* Ttd'ln1cal Spec1f'1cit1ons.

---,-4....... ~ICl~cll If,.idGr' tHU a1HI IJl-*r'iftllflHa

• f'.

RecardS of changes 1111d1 to Op1rat1 ng Procedures requ1 red l:ly Spec1f1cat1on S.8.1.

g.

Rteords of r1d101c:t1v1 sh1pm*nts.

n.

Records of s11ltd so~* and f1ss1on detector ltak tests and ~sul:s.

1

• Records af annual pny,s1c:a1 inventory of all s11l td sour~* rqtar1a1 of

-'-rec=o.;....;rd::.::*------

R.ec.orrfg o-F

~vi'ews p~r for,.,.,ec/ fdr c..l,o.n~'1S #l~e "f"o filf'"oc~tkres or rev;ec.J'0

--:~o~+-=-te_s_f<_s __

~--~e-'p~e_r_~r>'le--~_t_s~

1 ~f~"~~~~-Q_~_t_rc~o__....;.1o_c __

~e,......6i._o~.5__... ______ ~~----~--...J '

SALat

• UNIT 2 6-21 Amendment Na. ZS

INSERT TO SECTION 6.9.1 RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.9 The_Fxy limits for Rated Thermal Power (F~~P) for all

• core planes containing bank "D" control rods and all unrodded core planes, and the plot of predicted heat flux hot channel factor times relative power (F~*PREL) vs. Axial Core Height with the limit envelope shall be provided to the NRC Document Control Desk with copies to the Regional Administrator and the Resident Inspector.

The Report shall be provided to the Commission upon issuance (i.e., no later than coincident with the first application of the new Fxy limits).

In addition, in the event that the limit should change, requiring a new submittal or submittal of an amended Peaking Factor Limit Report, it will be submitted upon issuance.

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

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

a.

Records and drawing changes reflecting unit design modifications mad1 to systems and equipment described in th* Final Safety Analysis fo iocF~S'b.5' R1por

b.

Records of n1w and irradiated fuel inv1ntory, fu1l transfers and ass1111bly burnup histori1s.

c.

Records of radiation @xposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient or operational cycles,for those facility components identified in Table 5.7-1.

f.

Records of r1actor tests and experiments.

g.

Records of training and qualification for current members of the plant staff.

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of Quality Assuranc1 activities r1quir1 by the QA Manual.

I OEL.ETcDJi----

j.

t:tc.+Mfies o~ OS~(e..

'"~+:'°'f!S o.;:',*ts pr-edE'<.E'S~"r. tie Nuc..ler,.r-

k.

Records or"meeti ngs of th1 !s0Rcland "'!:ft~HiBo.

e11i1iet.J &-r-rl.

--~~~~~~~~~~

1.

Records for Environmental Qualification which art covered under the provisions of Paragraph 2.C(7) and 2.C(S) of Facility Operating Li c1ns1 OPR-75.

m.

Records of th1 s1rvic1 11v1s of all hydraulic and mechanical snubb1rs including th* dat1 at which th* s1rvic1 lift co111111nc1s and a~sociat1d installation and maint1nanc1 records.

n.

Records of s1candary wat1r sampling and water quality.

o.

R1cords of analysis required by th* radiological 1nvironmental monitoring program which would permit 1valuat1on of th1 accuracy of th* analysis at a lat1r dat1. This should includ1 proc1dur1s effe~ttv1 at sp1cif11d times and QA r1cards showing that th1s1 procedures w1r1 followed.

SALEM - UNIT 2 6-22 Amendment No. 68

r.Juc. leo.r ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel rad1at1on protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12

~IGH RADIATION AREA 6.12.l In lieu of the "control device" "'~"alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each hi~ radiation area in which the intensity of rad1ation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspieuously posted as a High Radiation Area and entran~

thereto shall be controlled by issuance of a Radiation Exposure Permit~. Any ind1vidua1 or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rat~ in the area.

b.

A radiation monitoring device wh1ch continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring devi:e may be made after the-dose rate level in the area *has been established and personnel have been made Knowledgeable of them.

c.

A health physics qualified individual (1.e., qualified* in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the faei11ty Meal;h ?hy51,ist iR t~*

Radiation Work Permit.

6.12.2 In addition t~he requirements of S.12.1, areas accessible to ~ersonnel with radiation levels such that a major *ortion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to revent unauthorized entr, and the keys shall be maintair.ed under the administrative contra o t e enio Shift Supervisor on duty and/or Senior Supervisor - Radiation Protection.

Doors shall remain locked except during pe~iods of access by personnel under an approved Rad1at1on Work Pennit which sMall spe~ify the dose rate ~evels in ~e innediate woric area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such.that a :najor portion of the boay could receive in one hour K Ii-,.-s, (S nor TYIO. tly ole.f=>l'.eJ a.5 -H.e Le-11!!. I a. f

.., J; ~fct r1 c. e

<> F 18 *' f1c.he!5

,f",,.,,1

-rhe so... r-c e or o..cc et;:~ ;J.k s I.A. i Fa.c.e *

. ersonnel or personnel escorted by personnel s.~all be exempt rom the RWP issuance r!qu1remen during the perfor:11ance of

~eir assigned ra *ation protection auties, pro ided they are other#ise f~11owing plant rac* tion protection ~rocedur for entry into high radia:ion a~eas.

n

/ *+

ll'.4o<<o..

~o..,

frofet:-fio,,

~~~~~-'----~~---'~

~.!,L~~ - UNIT 2 S-23 Amendment No. 28

I.

AOMINISTRAT!VE CONTROLS a dost 1n exc:ess of lOOO mrem~hat are loc:ated w1th1n large areas, suc:h as P'"'R c:onta 1 nment, where no enc:l osure exists for purposes of 1oc:k1 ng, and no enc:losure c:an be reasonable c:anstruc:Ud around the fnd1v1dual arus, then that area shill b* roped off, c:ansp1c:uously posted and a f1ash1ng light shall be ac:t1vated as a Wirn1ng d1vic:1.

In lieu of th* stay t1~ spec:1f1c:at1on of the RWP, d1rect or l"!ftlCltl (suc:h as use of c:losed c:1rc:u1t TV c:ameras) c:ont1nuous surve11lanc:1 may be made by personnel qualified in radiation protec:tion proc:1dures to provide positive exposure c:ontrol over th* ac:tiv1t1es within the aria.

5.l? PROCESS CONTROL PROGRAM (Pel')

5.13.1 The PO' sh~ll be approved by the Connission prior to i~1ementat1on.

6.13.2 Lic:ensee initiated c:h1ng1s to th* PO':

1.

Sh1li be sub*itted to th* CQlllll1ssion fn the Semiannual R1dioac:t1ve Effluent Release Rtport for the P*r1o4t in whic:h the cnange(s) *as 1111d*.

This submittal shall c:ant1in:

a. Suff1c:iently detailtd info~t1on ta tat1lly support the rationale for th* change without benefit of additional or supplemental in fonaati on:

b. A determination that th* c:hange did not reduc:e the overall c:onfol"'!lllnc:e of the solfdiffed waste product to tx1st1ng c:r1ter1a for solid WiStes~ and

c. Ooc:wnentation of th~ fact that the c:h1n91 has been reviewed and found acc1pt1ble by th* SORC.

2.

Shall b*com. effective upon revil'W and acc1ptanc:1 by the SORC.

5.14 OFrSIT! OOSE'CALCULATtON MANUAL {ODCM) 5.14.l The ODCM shall b* approved by th*.COll'lllission prior to implementation.

S.14*. 2 t. i cen see in it fated c:h1nges to th* 0004:

l.

Shilt be sublllfttld to th* Cann1ss1on fn th* Sem1annu1l

~ad1oact1ve Effluent Release Report for the period in which the c:hange{s) was

~de. This sublllitt1l shall cant1in:

a. Suffic:iently detailed fnfo~tion to totally support the rationale far the c:h1ng1 without benefit of additional or supplemental fnfo~tion. Inforin.tion subm1tted should c:onsist of a pacxage of

nose pages of the ODC't to be changed with eac:h page numbered and

~rovidtd with an approval and date box, together with appropriate an1lyses or evaluations justifying the c:hange(s);

• 9i<leasurement :nade at la" from sour~e of radi oac:t 1v1 t~.!....

SALEM

• Ul'HT 2 6-24 Amendment No. 28

ACMtNISTRArIVE CONTROLS

b. A det11"111n1t1on that th* change w111 not reduc1 the 1c:c:uracy or re111G111ty of dos.1 c.alc:uht1ons or satpo1nt ~ttrmfnat1on; and c:.

Oacuant1t1on of the fact th*t the dt1n91 "u O.en revf.,_ed and found 1cc:1pt1bl1 by the SORC.

2.

Sitall beceilai tffact1ve upan rev1tw 1nd 1ccept1nc1 by the SORC.

MAJOR 04AICG£S TO RADIOACTtVE LIQUID, W!OUS ANO SOLID WASTE iUATMEMT SYsttMS S.15.1 Lfc1ns1* 1n1t11ttdt111Jar d'l1nges to the rad101ctfv1 W1st1 systen (11qufd, gasaout 'ind so1fdJ:

. u

• 1.

SM11 be report.ct to the COIW1ss1an fn Ua~W for the period fn wttidt tJ'I* 1nlu1tfon WIS reviewed by (SCRC).

Tiie d1sc:ussfon of Heh c:hugel' sh111 c:onu 1 n:

1. A s~ry of the 1v1l1&1t1on that 1.ct to the detenr1n1tf on could 01 1111de fn 1cc:ord1nc:1 with 1~~"10.!9;

b. Suff1c:1tnt d9t1fltd 1nfor'!lllt1on to ta1:1lly support the reason for the dt1n99 without benefit of 1dd1t1on11 at' supp111119nta1 1nfat"INt1on; c:.

A detafltd description of the 1q11ipeent, c:011q2on1nts and proc:1ss1s 1""°1 vtd and tne 1 nter1'1ces with cine~ pl 1ft't syst1111S;

d.

An 1v1l1&1t1an at the c:h1n9*,..nidt snows the pred1c:t.ct,..hues of r-1df01cth* mtar111s fn liquid and gaseous 1f1'1uents and/or-quantity at solfd wast. that dif1'1r fra11 tnos1 pr*v1ousty p.-.di cttd f n tne 11 c:anse *PP 1 f c:atf an and.. ndlllents thereto:

An inl1&1tfon of tJ'I* dt1n91, wnfc:h snaws the upecttd 1111.xfrm.un 1sposu...s to fndiv1dull1 fn th* unrestrf cttd 1re1 and to the general popu11tfon tn1t dffftr frQI tnos1 pr.viously 1stflftitl1p/;11~ foct:tfi"ottS

/\\e~r e

ll~r;n5 SEMI ANNUAL RAO I OACTIVE EFFLUENT RELEASE REPORT*

+lie more pf,-5 fCJrit-focai-ion~, cit/

5.9.l:i-r Routine i:fadioactive Effluent Release Reports covering the operation of the unit during the previous six months of operation shall be submitted within 60 days after January 1.~nd July l of each year.

Th1 R 1adtoactiv1 Eff1u1nt R11tas1 R1ports shall includ* a summary of the quanti-ties of radioactiv1 liquid and gaseous effluents and solid waste released from the unit as out11nld in Regulatory Guide l.21. "Measuring, Evaluating, and

• A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common ta all units at the station; however, for units with separate radwaste systems, the subntfttal shall specify the releases of radioactive material from each unit.

• • fn liet1 ef sttamhs1on with tl'le AMt1al Rad1ele9ieal EAviFeAmeAtal QperatfAc; RelJQrt, tne 11ceAsee has the apt1en ef reta1AiA~ this su111Rary af reqyir1a tnetearele9)eal data en site iA a f1le that shall ~e prevideG t; tn1 NRC ~poa

• requ11t.

SALE?it - UNIT l 6-19 Amendment No. 59

ADMINISTRA7rVE CONTROLS Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in ~i~uid and Gaseous Ef'.luents from Li~ht-Water-Cooled Nuclear Power Pl~a,"

Revision 1, June 1974, with data su11111ar1zed on a quarterly basis following the format of Appendix B thereof.

s The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual surrmary of hourly meteorological data collected over the previous year. This annual surrmary may be either in the form of an hour-by*hour listing of magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured),

or in the form of joint fr~cy distributions of wind speed, wind direction, and atmospheric stability.

his same report shall include an assessment of tht radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of th* radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.l-3) during the report period.

All assumptions used in making these assessments (i.1., specific activity, exposure time and location) shall bt included in these reports. Tht meteorological conditions concurrent with th1 t1rne of r*least of radioactive mater ia 1 s in gaseous effl utnts (as dttermi ntd by samp 1-1 ng fr1qu1ncy and measurement) shall be used for determining th* gaseous pathway doses. The assessment of radiation doses shall bt performed in accordance with the OFFSITE DOSE CALCULATION MANUAL.

The Radioactive Effluent. R1leas1 Report to bt submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses frOlll primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating th* ~ose contribution frOlll liquid and gaseous 1fflu1nts art given in Regulatory Guide 1.109, Rev. 1, October 1977.

The Radioactive Effluent Release Reports shall include th* following information for each class of solid waste (as defined by 10 ~Part 61) shipped offsitt during the report period:

a.

Container volume,

b.

Total curie quantity (specify wh1th1r determined by measurement or

-estimate),

c.

Pr1ncipa1 radionuclides (specify whether determined by measurement

~

or estimate).

?

d.

Source of waste and processing employed (1.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

• U In 1 ;.eu of submission with the first half year Radioactive Effluent Release Report, the licensee has the option of retaining this su11111ary of required meteorological data on site in a file that shall be provided to SALEM - UNIT 1 Amendment No. ~

the NRC upon request.

AOMINISTRATIVE COIC"tR.OLS

e.

Type of container (e.g., LSA, Typ1 A, Type B, Large Quantity), and

f.

Solid1f1cation agent or absorbent (e.g., cement, urea formald~yde).

The Rad1oact1ve Effluent Rel1as1 Reports shall include a list of descr1pt1o~f unplann1d releases fra11 th* site to UNRESTRICT£D AREAS of rad1oactiv~ materials in gaseous and liquid effluents made during th* ~porting period.

Th* Radioactive Effluent Rel1as1 Reports shall include any changes made during the,_.porting p1r1od to the PROCESS CONTROL PROGRAM (PCP) and to the'OFFSITE COSE CALCULATION MANUAL (OOCM)~ as wt11 as a listing of new locations for dose calculations and/or 1nvironmental monitoring 1dent1f1ed by th* land use census pursuant to Specification 3.12.2.

SPECIAL REPORTS U.S. Nt/e.lear Qe~.,/4 fl.rt Ca,.,,m:"io11,,

Ooc::.,unetrl Co;ifrol /Jes1'71 Va.(;h,'11:jlr,"

D.c.

~o S"S"S', wi#i ~co fa fl.of' 6.9.2 Special rtports shall bl subm1tt1d to the Administrator Off1e1 within th* ti* period sp1c1fied for each report.

J,...__ ____

VStJR.C 6.lO RECORD RETENTION In addition to the app11cab11 record ret1nt1on r1qu1rement's of Title 10., Code of Federal Regulations, th* foll°"'ing records shall bl ret,.ined for at least the m1n1mwn period indicated.

~

s.10.1 The following records shall be retained for at least five years:

a.

Records and logs of unit operatic~ covering t11119 interval at each p-o~er level.

b.

Records and logs of principal maintenance act1 vi t1 es, i nsp1cti ons, repair and replacem.nt of principal items of equipment related to nuclear,safety. I evENTSj

c.

~

REPORTABLE etetfRRENtcs submitted to the Connission.

d.

e.

Records of surveillance activ1ti1s, inspections and calibrations required ~ these Technical Spec1f1cat1ons.

Oct..e-rt;.O~

f.

Records of changes made to Operating Procedures required by Spec1f1cat1on 6.8.l.

g.

Records of radi cacti ve shipments.

• n.

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

- i.

Records of annual physical inventory of all sealed source material of record.

0

~corol;-;F revi~r,JS p-;;;;r.11'1eJ Fo1 e./.a"ff"' ~

-fo fn:>~"'ures 0,.

re.,,leW!;' 0~

. ~

anti e')(pf!rims11+s/

~ur~ua.'1t" ro IOG~R,.oo.!lq, SALEM

• UN IT l o-Zl Amendmen.t No. 59

INSERT TO SECTION 6.9.1 RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.9 The Fxy limits for Rated Thermal Power (F~~P) for all core planes containing bank "D" control rods and all unrodded core planes, and the plot of predicted heat flux hot channel factor times relative power {F~*PREL) vs. Axial Core Height with the limit envelope shall be provided to the NRC Document Control Desk with copies to the Regional Administrator and the Resident Inspector.

The Report shall be provided to the Commission upon issuance (i.e., no later than coincident with the first application of the new Fxy limits).

In addition, in the event that the limit should change, requiring a new submittal or submittal of an amended Peaking Factor Limit Report, it will be submitted upon issuance.

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

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

a.

. Records and drawing changes reflecting unit design modifications

_made to systems and equipment described in the Final Safety Analysis Reper~ ' pursuaf'lf fo - 10 c.'FR s-o.s-q)

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient or operational cycles for those facility components identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members of the plant staff.

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of Quality Assurance activities required by the QA Manual.

j. li&eeerEls ef re*:iews perfermeEl fer ehaRges maae t:e preeeal:l:res eF

• eEtl:l:ipmeRt: er re::iews ef tests and experiments putsuant to lO*CFR

k.

1.

SG-M.

G.C. +ivifie5 or 0512 (a.;io/

Records of,£meetings ef t:he lsoRcl and.--t:h-e-~-IR-H!~ t"'lee/.i"JS "F ifs f're-

• dee. et;!;or, -t/.e /l)uc la::;_r Records for Environmental Qualification the provisions of Paragraph 6.16.

e11ie rol which are covered under

m.

Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.

n.

Records of secondary water sampling and water quality.

o.

Records of analyses required by the radiological environmental monitoring program which would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.

SALEM - UNIT 1 6-22 Amendment No. 93

ADMINISiRATIVE CONTROLS 6.ll RADIATION PROTECTION PROGRAM Procedures for personnel ra-diation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12

~IGH RADIATION AREA 6.12.l In lieu of the "control device"... -~lann signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each hig~r~diation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance -~

thereto shall be controlled by issuance of a Radiation Exposure Pennit~ny -

individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the* Qose rate 1 evel in the area has been established and personnel have been made knowledgeable of them.

c.

A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation* dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall pe.rform periodic radiation surveillance at the frequency specified by the f~cil;ty Health P~)9ie1s; ;A ti'te Radiation Work Permit.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel

[iJ-with radiation. leve1s*such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locJc.ed doors to N~~te~r revent unauthorized entry, and the keys shall be maintained under the administrative contra o t e en or Shift Supervisor on duty and/or Senior Supervisor

• Radiation ?rotection. Doors shall remain locked except during periods of access by personnel under an approved Radiation Wo~ Per.nit which shall specify the dose rate levels in the irrmediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel wi~h radiation levels such that a major portion of t~e body could receive in one hour k Thts ts n.t>rmAlly k*F;,,,ec/ Q.'5 ~

!eve.( Q..T Q,, ol.-r;-/QAce t>F 18 11'1ches Fr"D,..,

the Soun:.e e>r a.1:.c..ttt;s;6/~ surFa.'-.e.

~~

Personnel or perscnnel*escorted by shall be exempt om the R~P issuance requirement their clssigned ra tion protection duties, provi ed they ~re other~ise following plant racia *on protection procedures or entr1 il"to ni;h raciclt;ior.

area 5 *

£oo(l'ct:f--lotf fro fec.f;"..,

SALC:1'1

• UNIT 1 6-23 Amencment ~o. 59

ADMINISTRATIVE CONTROLS a dose in exces~f 1000 mrem......lthat are located within large areas, such as PWR containment,_;where no enclosure exists for purposes of locking, and no enclosure can be reasonable constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13. PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee initiated changes to the PCP:

1.

Shall be submitted to the Commission 1n the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made.

This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional'or.supplemental infonnation; b*.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and

c. Documentation of the fact that the change has been reviewed and found acceptabl~ by the SORC.

2.

Shall become effective upon review and acceptance by the SORC.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM}

6.14.l The OOCM snall be approved by the Conmission prior to impleme~tation.

6.14.2 Licensee initiated changes to the OOCM:

1.

Shall be submitted to the Conmission in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made.

This submittal shall contain:

a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.

Information submitted should consist of a package of those pages of the OOCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change(s);

'*Mentsreme"t made at; 18 11 frem satsree ef radi eaethi ty, SALEM - UNIT 1 6-24 Amendment No. 59

~

ADMINISTRATIVE CONTROLS

b. A d'!t~rmination that the change will not reduce the accuracy or relfability of dose calculations or setpoint determination; and

c. Documentation of the fact that the change has been reviewed and found acceptable by the SORC.

2.

Shall became effective upon review and acceptance by the SORC.

6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS ANO SOLID WASTE TREATMENT svsTEMs 6.15.1 Licensee initiated major*changes ta the radioactive waste system (liquid, gaseous and saliU):

IJ

l.

Shall be. reported to the Commission in thevFSAR for the period in which the evaluation was reviewed by (SORC).

The discussion of each changel}shal 1 contain:

+""'+ +i'1 cAo.r19e

a. A summary of the evaluation that led ta the determination could be made in accordance with lO""'CFR ~50.59;

b. Sufficient detailed information ta totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;

d.

An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

e.

An evaluation of the change, which shows the expected maximum exposures to individual in the unrestricted area and ta the

.general population that differ from those previously estimated in the license application and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual

. releases for the period prior to when the changes are to be made;

g.

An estimate of the exposure to plant operating personnel as a result of the change; and

h. Documentation of the fact that the chang_e was reviewed and found acceptable by the (SCRC) *

2.

Shall become effective upon. review and acceptance by the SCRC.

SALE~ - UNIT l 6-25 Amendment No. 59

\\.

ADMINISTRATIVE c.oaTROLS 6.16 ENVIRONMENT-~-QUALIFICATION 6.16.l By ~elater thaA JijAe 30, 19e2Z11 safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of:

Division of Operating Reactors "Guidelines for Evaluat-ing Environmental Qualification of Class lE*Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 "Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment,w December 1979.

Copies of these documents are attached to Order for Modification of License No. DPR-70 dated October 24, 1980.

!!~!/ /

6.16.2 By Ro liter tRaR Decambar -1, 1980, ~omplete and auditible records mY-St be available and maintained at a eefitral location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail ta document the degree of compliance with the DOR Guidelines or NUREG-0588.

~eru1'tec..r.Such records should be updated and maintained current as equipment 1s replaced_, further tested, *or otherwise further. qualified.

SALEM - UNIT l 6-26 Amendment No. 59