ML20244B118

From kanterella
Jump to navigation Jump to search
Modified Proposed Tech Specs 3/4.6.1.1, Primary Containment & 3/4.6.5.1, Secondary Containment, Listing Devices Affected by Proposed Changes
ML20244B118
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 05/31/1989
From:
DETROIT EDISON CO.
To:
Shared Package
ML20244B117 List:
References
NUDOCS 8906120290
Download: ML20244B118 (9)
v • d • e


Text

, - - .

I s, i

(

i PKPQGED PME CHMMS 1

l Os' ,

(

8906120290 890531 PDR ADOCK 05000341 P PDC

/_

CONTAINMENT SYSTEMS 3/4.6 CONTAINMENT $YSTEMS 3/4.6.1 PRIMARY CONTAINMENT PRIMARY CONTAI MENT INTEGRITY

=

LINITING CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAl m ENT INTEGRITY shall be maintained.

OPERATIONAL CONDITIONS 1, 28 and 3.

APPLICABILITY:

ACTION:

Without PRIMARY CONTAINMENT INTEGRITY, restore l

I CCLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.1 PRIMARY CONTAlleiENT INTEGRITY shall be demonstrated:

a.

After each closing of each penetration subject to Type B testing, except the primary containment air locks, if opened following Type A or B test, by leak rate testing the seals with gas at P,, 56.5 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Su combined leakage rate is less than or equal to 0.60 L,.

tr.

    • 1 east once per 31 days by verifying that all primary conteainment penetration #* -at capable of being closed by OPc.osed during accident See L , y y-automatic isolation valve. .-d -*aufrad..toosea v.b;;. Mank flanges, or g conditions are closed bvalves secured in position, except .; ;*avided ~

deactivate .6.3-1 of Specification 3.6.3.

e

c. By verifying each primary containment air lock is in compliance with the requirements of Specification 3.6.1.3. l
d. By verifying the suppression chamber is in compliance with the requ i ments of Specification 3.6.2.1.
  • See Special Test Exception 3.10.1. hich a l

2%c;' valves, flanges, and deactivated automatic va ves w cured in the inside the cons.t ' t- and are locked, sealed or oied closed during each COLD closed position. These penet.4S- shalle ..rM d not us p r 'a w d when the primary SHUTDOWN except en inerted since the last verificat6.. - mare of ten 3/4 6-1 FERMI - UNIT 2

w ,

,'c ';

?-

1 Insert A f7g j, % gg g.f,/,/ / '

b. At least once per 31 days by ve fyingLthat all primary .

containment penetrations.ene those inside the containment or in locked high radiation are t capable of being closed by CFEMBLE containment' automatic isolation valves and required to be-l .

closed during accident conditions are closed by locked closed valves, blank flanges,- or deactivated automatic valves secure 5 in l

1- position, except as provided in Table 3.6.3-1 of specification 3,. 6 . 3 .

1. Valves, flanges, and deactivated' automatic valves which are located inside the containment, and are locked, sealed' or otherwise secured in the closed position stall be verified .

closed during each C(ID SHUIDOST except such verification need not be performed'when the primary containment has not been deinerted since the last verification' or more' often thar once

'...- per 92 days. (f,gg .. 7,ye 4/,(,,/,/-/)

2. Incked closed valves, flanges,:and deactivated automatic valves which are located outside the containment within locked high radiation areas shall be verified closed during each SHUIDOWN if not performed within the previous 31 days.

p.:225rr L- 2r' 9 =:= -h.ich ::--t. Lip. ::'i; tim n:n'

'ni .;; '" - ==== - ; M =rif fM b; rrir Of hip

'i:tir. == rer: ere:1:.

l tt The Tl? Flsnt. (Psnsidbn X-ESA)I may be vedbil & "I'"' *b high mlENn area access conhv/r V He TIP R**m rema;nr a lockc/

high nd&/dn am &&ng cup warpw.

i 1

^ -- - - - _ - - - _ . - - - -

, ISBLE 4.6.1.1-1 PRIMARY COTI'AIIMENT ISOEATION VALVES /FLAtGES LOCATED IN LOCKE0 HIGH RADIATIONS AREAS PLANT IDDEIFICATION VALVE NUMBER LOCATION PDETRATION

a. 1. P34-F013 BWCU valve X-48F
2. P34-F014 Pit b . 1. E21-F023A Reactor Bldg. X-16B
2. E21-F022A Second Floor c . 1. G33-F002 RWCU Valve X-43
2. G33-F003 Pit d . 1. B21-F017 Steam X-8
2. B21-F018 Tunnel
e. 1. T48-F006A Reactor Bldg. X-15
2. T48-F007A Second Floor f . 1. C41-F026 BWCU Valve X-42
2. C41-F027 Pit
91. B21-F025A Steam X-7A, B, C & D
2. B21-F025B Tunnel
3. B21-F025C
4. B21-F025D
5. B21-F026A
6. B21-F026B
7. B21-F026C
8. B21-F026D
h. 1. B21-F102A Steam X-7A
2. B21-F103A Tunnel i . 1. G33-F122 Steam X-9B
2. G33-F123 Tunnel j . 1. E51-F036 Steam X-10
2. E51-F037 Tunnel k . 1. E41-F014 Steam X-11
2. E41-F015 Tunnel
1. Penetration X-35A TIP Roam X-35A Blank Flange 1

3/V 6- / 6

i t .> .' V  !

hW ** ,

J. f g ,

py!  ;

g CONTAINMENT SYSTEMS j J

4#

3/a.6.5 SECONDARY CONTAINMENT' SECONDARY CONTAINMENT INTEGRITY )

LIMITING CONDITION FOR OPERATION' j

3.6.5.1 : SECONDARY CONTAINMENT INTEGRITY shall'be maintained.'

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2,-3,.and *.

)

ACTION:

Without SECONDARY CONTAINMENT INTEGRITY: f a.

In OPERATIONAL CONDITION 1, 2, or 3, restore SECONDARY CONTAINMENT j INTEGRITY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within.the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. In Operational Condition ._*, suspend ha'ndling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations The provisions of with a potential for draining the reactor vessel.

- Specification 3.0.3 are not applicable.

_ SURVEILLANCE REQUIREMENTS 5 4.6.5.1 SECONDARY CONTAINMENT INTEGRITY shall'be demonstrated by: ~

j

a. Verifying at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the vacuum within' the secondary j containment is greater than or equal to 0.125 inch of. vacuum' water gauge, b.- Verifying at least once per 31 days-that:  ;

1.

All secondary containment equipment hatches'and pressure-relief j doors are closed and sealed and one railroad bay access door.is j closed. .

/,

I

2. At least one door in each access toLthe condary contai ffh/ 197, 6 gdY. /, m,.,.  !

is closed. e n tf 7 .,u,,f -

-~ ,

l 3.

All secondary containment penetrations 4not capable of b ,eing closed by OPERABLE secondary containment automatic isolation dampers / valves and required to be closed during accident conditions are closed by valves, blank flanges, or deactivated -

p gau m gic dampers / valves secured in the closed position.

At least once per 18 months: I

d. K.
1. Verifying that one standby gas treatment subsystem will draw down ,

the secondary containment to greater than or equal.to 0.25 inch l of vacuum water gauge in less than'or equal to 567 seconds at a l flow rate not exceeding 3800 cfm, and l

2. Operating one standby gas treatment' subsystem for 1. hour and main- ,

l taining greater than or equal to 0.25 inch of vacuum wate

  • When irradiated fuel is being handled in the secondary co 3/4 6-51 FERMI - UNIT 2

,. n *

' n.. s

-l

, rg

' ijj  ;

l i

Insert B .

alves, flanges, and. deactivated automatic isolation ,

j danper ahQh are located within locke6 high radiation '

areas and required t h as described..in section 4.6.5.1 shall be verified closed during eac .

if not performed within the previous 31 days.

C %r[yiq $leAm Tunnel % cal PaneIs are- closed dar'wg each COLP $guTDOWAl }f nof perhr$1 (UIk !!' N E fr N/0VJ ?I b (S. j j

1 5 l h.

n.

g ,

j

  • ~ '

T hU, "? -

E MSES /ySERT 5//.(a,/ll 9 3/4.6 CONTAINMENT SYSTEMS' i

[~ BASES 4

~

3/4.6.1 PRIMARY CONTAINMENT j 3/4.6.1.1 PRIMARY CONTAINMENT INTEGRITY f PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive mate-rials from the containment atmosphere will be restricted to those leakage paths i and associated leak rates assumed in the safety analyses. This restriction,  ;

in conjunction with the leakage rate limitation, will limit the_ SITE BOUNDARY radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

4.6.1.2 PRIMARY CONTAINMENT LEAKAGE  ;

The limitations on' primary containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure of 56.5 psig, P,. As an added conserva-tism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L, during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.

Operating experien:e with the main steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the speciel requirement for testing these valves.

The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J of 10 CFR Part 50 with the exception of exemptions granted for main steam isolation valve leak testing and testing the airlocks after each opening end analyzing the Type A test data.

Appendix J to 10 CFR Part 50, Paragraph III.A.3, requires that all Type A tests be conducted in accordance with the provisions of N45.4-1972, " Leakage- ,

Rate Testing of Containment Structures for Nuclear Reactors." N45.4-1972 requires that Type A test data be analyzed using point to point or total time analytical techniques. Specification 4.6.1.2a. requires use of the mass plot analytical technique. The mass plot method is considered the better analytical  ;

technique, since it yields a confidence interval which is a small fraction of j the calculated leak rate; and the interval decreases as more data sets are added to the calculation. The total time and point-to point techniques may give con- -

fidence intervals, which are large fractions of the calculated leak rate, and the intervals may increase as more data sets are added. l The mess plot method is endorsed by ANSI /ANS 56.8-1981 (Containment System <

Leakage Requirements) which superseded N45.4-1972. l 3/4.6.1.3 PR1HARY CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the primary containment air i locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY  !

and the primary containment leakage rate given in Specifications 3.6.1.1 and I

FERMI - UNIT 2 B 3/4 6-1 Amendment No. 8 4 1

j

1~ ,,

y.

' U- J'

]};[r.-I ,

xq ;t:. ,

N vfs
  1. maw FGt BA5mR 3/4.6.1.1 -

PRIl%RY CONIAIINCNT INITGRITY is demonstrated.by. leak . rate testing land :c by verifying-that all primary containment'. penetrations not capable of.

being' closed by OPERABLE containment automatic isolation' valves and-required to be closed during accident conditions;ar.e closed by locked, valves, blank flanges or deactivated automatic valves secured'in the.

. closed position. For test, vent and drain' connections which are part;-

of the containment boundary, a_ threaded pipe cap in' addition to the3 containment isolation valve (s) provides protection equivalent to a.

blank flange. .

t i

l

~!

a J

l i

i i

___--.-_____ __-___-_ ____ : - -_l O

.l

-. . INDEX

, l l

I LIST OF-TABLES (Continued)'

_{

TABLE s PAGE 3.3.7.9-1 FIRE DETECTION INSTRUMENTATION.................. 3/4.3-68 3.3.7.11-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION .................... ........... 3/4 3-72 4.3.7.21-1 RADIOACTIVE LIQUID EFFLUENT MONITOR NG-INSTRUMENTATION SURVEILLANCE REQUIREMENTS ...... 3/4 3-74 3.3.7.12-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING i INSTRUMENTATION .............. . ..................'3/4 3-77 1 4.3.7.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ...... 3/4 3-81 .

3.3.9-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION'................................ 3/4 3-87 .

3.3.9-2 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS . . . . . . . . . . . . . . . . . . . . . . . ' 3/4 3-88 l 4.3.9.1-1 FEEDWATER/ MAIN TURBINE. TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS ...... 3/4 3-89 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE VALVES'......................... ISOLATION 3/4 4-12 i

3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAK PRESSURE MONITORS .......................... AGE .... 3/4 4-12 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS ........ 3/4 4-15 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM ............................... 3/4 4-18 ..

4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM--

WITHDRAWAL SCHEDULE ............................ 3/4 4-22 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES . . . . . . . . . . . 3/4 6'22 3.6 S.2-1 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAMPERS . . . . . . . . . . . . . . . . . . . . 3/4 6-53

{ 3.7.3-1 SURVEY POINTS FOR SHORE BARRIER . . . . . . . . . . > . . . . . 3/4 7-12 3.7.7.5-1 FIRE HOSE STATIONS ............................. 3/4 7-32 3.7.7.6-1 ' YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES .................................... 3/4 7-37 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE . . . . . . . . . . . . . . . . . 3/4 8-8 FERMI. , UNIT ,2, --

._- /

xxiv n

4. 6.l.)-l PSIWM CCNTAU(MEUT TsoLATWI VALVES

/W L.ocRED HIG11 VDIATwAf MEAS . . . . - -

3l'l 6

  • lb f lIRkkGG b- s

_ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . '

Retrieved from "https://kanterella.com/w/index.php?title=ML20244B118&oldid=3107828"