Text

Proposed Tech Specs for Units 1 & 2 Re Mod of Frequency of Type a Containment ILRT
	ML18101B336
Person / Time
Site:	Salem
Issue date:	04/22/1996
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18101B335	List: ML18101B334; ML18101B336;
References
	NUDOCS 9604290189
	Download: ML18101B336 (8)
	v • d • e

Document, Control LR-N96071

'Attachment 3 LCR S96-04 SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS INCORPORATION OF 10CFR50 APPENDIX J OPTION B TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications are affected by this requested amendment:

Facility Operating License No. DPR-70 (Unit 1)

Technical Specification Page 4.6.1.2 3/4 6-2 4.6.1.2.b-e 3/4 6-3 4.6.1.2.f 3/4 6-4 4.6.1.6.1 3/4 6-8 Facility Operating License No. DPR-75 (Unit 2)

Technical Specification Page 4.6.1.2 3/4 6-2

4. 6 .1. 2. b-g 3/4 6-3 4.6.1.6.1 3/4 6-8 9604290189 960422 PDR ADOCK 05000272 ~.,

P PDR *1 .

CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION

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

3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of s La, 0.10 percent by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at design pressure, (47.0 psig).

b. A combined leakage rate of s 0.60 La for all penetrations and valves subject to Type Band C tests as identified in Table 3.6-1, when pressurized to Pa.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore the leakage rate(s) to within the limit(s) prior to increasing the Reactor Coolant system temperature above 200°F.

0 r-I ACl:.O~DAN.Cf_ w \l~ I 0CF~50.s"-I. (o) AT A- TES* '

t

$CYl~IA-1...L 't>E:.-'\'CAl"'l*M~D i'-l C.i:n*l.F~~li1 A-M~ W \~ APf~OIX, j

==~~~~=~~ =~~i~~ii~=-i:ii~£~~i~G:;~7~~~=i;.~.;,;;: £e_

4.6.1.2 The containment leakage rates shall be demonstrated at the following est schedule and shal e etermined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 +/- 10 month intervals during shut~otom at design pressure (47.0 psig) during each 10-year service period.*(**)

The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.

The second inservice Integrated Leak Rate Test shall be performed at the fifth refueling outage, but no later than May, 1984.

- The fifth inservice Integrated Leak Rate Test (the second inservice Integrated Leak Rate Test during the second 10-year plant inserJ~ce inspection interval) shall be performed during the thirteenth refueling outage, but no_ later than June 1997.

SALi::M - UNIT 1 3/4 6-2 Amendment No. 171

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. If any periodic Type A test fails to meet .75 L , the test schedule for subsequent Type A tests shall be r~viewed and approved by the Commission. If two consecutive Type A tests fail to meet .75 L , a Type A test shall be performed at least every 18 months un~il two consecutive Type A tests meet .75 L at which time the above test schedule may be resumed. a

c. The accuracy of each Type A test shall be verified by a supple-mental test which:

l. Cor1firtrr.: the c;.ccuracy of tre Type A test by verifying that the differ*ence between supplemE:!ntal and Type A test data is within 0.25 La.

2. Has a (;tir*ci."i:ion <;pffir.ic1*.t tr' f'Stfl!*li.sh ri.ccurately the change in le;;ka~r* :.ci.\*!r.:r.n u*1c:: Typ"."* A tw:*L. c-nd the supple-men ta 1 test. .

3. Requires the quantity of g~s injected intQ the containment or bled from the conto.in;*,;,"'.t1t during the supr1ementai test to be equivalent to at l~ast 25 percent of the total j measured le2kage rate at dPs~gn pressure (47.0 psig).

a.I* Type 8 and C test~ s:*!::i*i be conc!uC.ed v i 1)1 gas at design pressure 1

(47.0 psig) at intervals no greater than 24 months except for tests involving air locks.

Air locks shQll be testE:!d and demonstrated OPERABLE per Surveillance RE!quirernent 4.6. l. 3.

SALEM - UN IT l 3/4 6-3

CONT.A.INMENT SYSTEMS SU RV EI LLANCE REou*r REMENTS (Continued)

All test leakage rates sha11 be calculated using obser*l"ed ~

converted*~o absolute values, Error analyses shall be per- /

fonned to select a balanced integrated leakage measurement system.

\ )

I J/ SALEM - UNfT l 3/4 6-4

e CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION J.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.~.

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

ACTION:

With the *tructural integrity of the containment not conforming to.the above requirement*, re*tor* the structural integrity to within the limits prior to increa*ing the Reactor Coolant System temperature above 200°F.

SURVEILLANCE REQUIREMENTS 4.6.1.6.1 Containment Surfaces The structural integrity of the exposed

-acces*ibl* interior and exterior *urfac** of the containment, including the liner plate, *hall be determined d~*isg th* *INedewn !e~ eaea 'l'ype A*

eeneainmene l*.-..9* EAC* te*t (reference SpecLfLcacLan 4.6 1.~) by a visual in*pection of th*** *urfac*** This in*pection *hall be performed prior to the Type A containment leakage rate test~o v~ify no apparent changes in appearance or other abnormal degradation. ('L~~fl'ltf ~,y.,c.A.""'\\'1>"( '\*IP*\*"2.)

Repo;t*- Any abnormal degradation of the containment structure detected during th* above required inspection* *hall b* evaluated for reportability pur*uant to 10CFRS0.72 and 10CFRS0.73. Th* evaluation shall be documented and shall include a description of the condition of the concrete, th* inapection procedure, th* tolerance* on cracking, and the corrective action taken.

"i:.O:.I 1~ PC~Fo~.l"'I E:~ AT /o )"llAL.

I "\.IE:-P..VAL- 7 \w o At>~1T1 c;>rl It L- ,,..., ~Pi:c.11 oAI S. ~hA<.. '- b E.

I re<t~ ~Mi;.\;'.> ,+\ A f'?R.o)I. 1..N\A"\~L )I f:.6?'-lAL '"'lllZRl/A L ~

t> vtR\ ~ G- SJ.iurJ>owNS ~~ &;£,--t "\"y\>f: A "TE&,-?,

SALEM - UNIT l 3/4 6-8 Amendment :*::

133

CONTAINMENT e?TEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage ~ates shall be limited to:

a. An overall integrated leakage rate of less than Qr equal to La, 0.10 percent by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at design pressure (47.0 psig).

b. A combined leakage rate of less than or equal to 0.60 La for all penetrations and valves subject to Type B and C tests as identified in Table 3.6-1, when pressurized to Pa.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore the overall integrated leakage rate to less than or equal to 0.75 La and the combined leakage rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 La prior to increasing the Reactor Coolant System temperature above 200°F.

SURVEILLANCE REQUIREMENTS The containment leakage rates shall be demonstrated at the following est schedule an s a e eterm1ne n con ormance with the criteria specified in Appendix J of 10 CFR SO using the methods and provisions of ANSI N45.4-1972:

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 +/- 10 month intervals* during shutdown at design pressure (47.0 psig) during each 10-year service period.

The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.

The test interval for conducting a Type A test shall be extended from 40 +/- 10 months to allow the third Type A test, within the first 10-year service period, to be completed during the 10-year plant in-service inspection outage (6th refueling outage). This extension expires upon completion of the 6th refueling outage.

~'~ IDC'FR..5'D1'::>-"-/(o) ,41 A[~::;.-,-

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. If any periodic Type A test fails to meet .75 L, the test schedule for subsequent Type A tests shall be reviewed aRd approved by the Commission. If two consecutive Type A tests fail to meet .75 La, a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet .75 La at which time the above test schedule may be resumed.

c. The accuracy of each Type A test shall be verified by a supplemental test which:

1. Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 La.

2. Has a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.

Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage rate at design presS'Ure (47.0 psig).

Type B and C tests shall be conducted with gas at design pressure (47.0 psig) at intervals no greater than 24 months except for tests involving air locks.

11 Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6. 1.3.

f. All test leakage rates shall be calculated using observ8~ :ata converted to absolute values. Error analyses shall be performed to select a balanced integrated leakage measurement system.

g. The provisions of Specification 4.0.2 are not applicable.

SALEM - UNIT 2 3/4 6-3

~NTAXNMENT SYSTEMS CONTAINMENT SIRUCTURAI. INTEGRITY LIMITING CONDITIONS FOR OPERATION

- - - - a*************************************

3.6.l.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: HODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment not conforming to the above requirement*, restore the structural integrity to within the limit* within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hour* and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.6.1 Containment Surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined dYEiRg ~he ah~~dewn fer each ~ype A aeR~aiRIReR~ leakage ra~e ~es~ (refereftee Speeifica~ion 4.6.1.2) by a visual inspection of these surfaces. This inspection shall be performed prior to the Type A containment l_eakage rate test1Co verify no apparent changes in appearance or other abnormal degradation. (~~'Y~tl-tlit-f.. ~fCC.\~,'c...~::-r10 ...I 'f,j.,\,2.)

Reports Any abnormal degradation of the containment structure detected during the above required inspections shall be evaluated for reportability pursuant to 10CFRS0.72 and 10CFRS0.73. The evaluation shall be documented and shall include a description of the condition of the concrete, the inspection procedure, the tolerances on cracking, and the corrective action taken.

-:S:.\= '\Y\~ TYPL A \e-:.T 1~ ?e~H:.R~E.-1) A\ 1E> )'ri:A~

11'-\"\SR.\lftL-? 1 \wo A't>~l""r~'Dr-lAL. 1r.l~?ec...."\1ei"" ~ $\.,A<.L l:>'f...

'\>C.R.~11..llAt::.l'> AT A'i"P~1>1){1.Nf~~E.L.-y ~G?'-\..+L IN"t~A.VAL..'S:>

\) I.\. ~\ f't tp... $ 'h"'-"'r1J) f:> U> N ~

~i:,"\w~,-..\ \-yP,E_ A \il::is.~

SALEM - UNIT 2 3/4 6-8 Amendment No. 112

ML18101B336

Text

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

Navigation menu

Search