ML20034F963
| ML20034F963 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/01/1993 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20034F962 | List: |
| References | |
| NUDOCS 9303080005 | |
| Download: ML20034F963 (7) | |
Text
{{#Wiki_filter:. _ i l'Y-CEI/NRtt-/5 74 L CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE f*3el ef 7 f5 LIMITING CONDITION FOR OPERATION l 3.6.1.2 Primary containment leakage rates shall be limited to: l Ca s-lef t) An overal1 integrated leakage rate of less than or equal to 0.75 L '*b'"* l'I5 a. 4 a 0.20 percent by weight of the primary containment air per 24 hours at P,11.31 psig. 3 b. A combined leakage rate of less than or equal to 0.60 L for all a penetrations and all valves, except for main steam line isolation valves and valves which are hydrostatically leak tested, s' bject'to u Type B and C tests when pressurized to P,11.31 psig. 1 a c. Less than or equal to 25 scf per hour for any one main steam line through the isolation valves when tested at P,,11.31 psig. d. A combined leakage rate of less than or equal to 0.0504 L, for,all penetrations that are secondary containment bypass leakage paths when pressurized to the required test pressure. e. A combined leakage rate of less than or equal to 1 gpm times the total number of containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested atal.10 P,, l g' 12.44 psig. G reater than er et"'I +*) APPLICABILITY: OPERATIONAL CONDITIONS 1, 9 and 3x, wHh & reacf,r c.,la t W '"
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"'" F * "" # " Y* ACTION: i i With: (as-lef t] The measured overall integrated primary containment leakage rate N j l a. 4 exceeding 0.75 L, or a b. The mea.sured combined leakage rate for all penetrations and all l valves except for main steam line isolation valves and valves which are hydrostatically leak tested, subject to Type B and C tests l l exceeding 0.60 L,, or c. The measured leakage rate exceeding 25 scf per hour for any one main steam line through the isolation valves, or d. The combined leakage rate for all penetrations that are secondary containment bypass leakage paths exceeding 0.0504 L,, or e. The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment exceeding i gpm times the total number of such valves:
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b E ; Syc o.1 Tm n R C ;. 3.10.1 [ l PERRY - UNIT 1 3/4 6-3 Amendment No. 44 i 9303080005 930301 PDR ADOCK 05000440 l .P PDR
l 1 P Y-C.2Z /Ju R tt -IF % L ' CONTAINMENT SYSTEMS A
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P=3e A of 7 LIMITING CONDITION FOR OPERATION (Continued) G e, : ~ gCTION (Continued) Restore the leakage rate to less than or equal to the above limit (s) within 1 hour or be in at least HCYr l SHUTDOWN within the next 12 hours and in COLD SHUTDOWN estor _ ithin the following 24 hours. w The overall integratec teakace rate (s) to less than or equal to n.75 L * ""d a b. Tne cc.. ined leakage rate for all penetrations and all valva, except for main s. =m line isolation valves and valves which .ydrostati-cally leak tes. d subject to Type B and C tests ta ss than or l equal to 0.60 L,, - d c. The leakage rate to less t.._ 25 scf nour for any one main steam line througn the isolation val nd d. The combined leakace ra+ .or all pene
- ions that are secondary containment bypass 1 _(age paths to less th -
r equal to 0.0504 L ' a and I The co ..ed le'akace rate for all containment isolation ves in e. hvd. statically tested lines which penetrate the primary cc.. *nment l so less than or equal to 1 gpm times the total number of such v s, < or to increasing reactor coolant system temperature above 200*F. SURVEILLANCE REOUIREMENTS Levers tl se-le f t a.L a s-f on.k int e n e st= Q u k <rr reva k e s cm e t "=c Q 4.6.1.2 The primary containment seenage rates sh oe cemonstratec at tne ll 4 following test schedule and shall be determined conformance with the cri-teria specified in Appendix J of 10 CFR Part 5 sing the methods and provi-ll sions of ANSI N45.4-1972 and SN-TOP-1; test results shall also be reported based on tne Mass Point Methodology described in ANSI /ANS H56.8-1981: a. Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 + 10 month intervals during shutdown at P ' a 11.31 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. TA= everall as-lef t' inte3r.+e4 pria. ry centainmentl le.bage raft shall be less An er egal f. o.v.Lgoe.. As) R b. If any periodicjType A test ? n -.;n C.7 Aa, the test schedule ll tas-f.. Ar for subsequent Type A tests shal' be reviewr_ and approved by the Commission. If two consecutiveVTvre A tests r
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i a R m -+. -- n 3 Type A test shall be performeo a east every 18,mo,n%,s,guntil two fu-ta W consecutiveTType A tests meet L, at which time the above test l a senedule may be resumed. i c. The accuracy of each Type A test shall be verified by a supplemental test which: r .C% W PERRY - UNIT 1 3/4 6-4 Amendment No. 44
i t I P y - C E.r/AJ R R - f r 74 L A ff a.ch s,_wi.R j a 3/4.10 SPECIAL TEST EXCEPTIONS i hje 3 et,7 g@;; 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY /DRYWELL INTEGRITY l LIMITING CONDITION FOR OPERATION 3' a., 3.10.1 The provisions of Specifications 3.6.1.1.1,. C.. r 3.6.1.3, 3.6.2.1, ll 3.6.2.3, 3.6.5.1, 3.6.5.2, 3.9.1 and 3.9.3 and Table 1.2 may be suspended to permit the reactor pressure vessel closure head and the drywell head to be removed and the drywell air lock door to be open when the reactor mode switch is in the Startup position during low power PHYSICS TESTS with THERMAL POWER l less than 1*4 of RATED THERMAL! POWER and reactor coolant temperature less i than 200ep, APPLICABILITY: OPERATIONAL CONDITIONS 2 and 5, during low power PHYSICS TESTS or snutcown margin demonstrations. 5 ACTION: d With THERMAL POWER greater than or equal to 1% of RATED THERMAL POWER or with the reactor coo'lant temperature greater than or equal to 200 F, immedia M y place the reactor mode switch in the Shutdown position. l h ~ ie 1 ~ a i i l 1 1 SURVEILLANCE REQUIREMENTS i i 4.10.1 The THERMAL POWER and reactor coolant temperature shall be verified to be within the limits at least once per hour during low power PHYSICS TESTS or shutdown margin demonstrations. i t PERRY - UNIT 1 3/4 10-1 i ~.
i P y -C E I/N A R - /5'76 L 1 3.4.6 CONTAINMENT SYSTEMS h ff ad un Y .2. F"P'
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3/4.6.1 CONTAINMENT } 3/4.6.1.1 PRIMARY CONTAINMENT INTEGRITY i PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to tnose leakage - i paths and associated leak rr-assumed in the accident analyses. This restriction, in conjunction .c. the leakage rate limitation, will limit the site boundary radiation doser o within the limits of 10 CFR Part 100 during accident conditions. During shutdown when irradiated fuel is being handled in the primary l containment, and during CORE ALTE?ATIONS and operations with a potential for draining the reactor vessel, the f footnote pemits the opening of six vent and drain pathways for the purpose of perfoming containment isolation valve leak rate surveillance testing provided the reactor has been subtritical for t at least seven days. Offsite doses were calculated assuming the postulated fuel handling accident inside primary containment after a seven day decay i time, and assuming all the airborne activity existing inside containment after the accident is immediately discharged directly to the environment (i.e., no containment). Although this analysis would indicate that no restriction on i the number of vent and drain pathways was required, the number of open pathways was restricted to six for conservatism. V ] The %s f e== A* le ki3e. raie for Type A ) l e k =3 e tesis is I,o L., iv k/s h c,rreef eaAs {
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3/4.6.1.2 CONTAINMENT LEAKAGE Jtes,ated le k =3s raf e, j { The limitations on containment leakage rate ensure that the total contain-ment leakage volume will not exceed the value as med in the accident analyses at the peak atrident ores:ure of 11.31 psig, P. As an added conservatism, the a L ["as laf tM _overai gintegrated 'eakage rate is further limited to less than or m.-.. equal to 0.75 La during performance of the periodi tests to account for possible degra.dation of the :ontainment leakage bar iers between, leakage tests. Tyra AM Overall integrated leakage rate means the leakage rate which obtains from a summation of laakage through all potential leakage paths. /here a leakage ll patn contains more than one valve, fitting, or component' ir series, the leakage for that path will be that leakage of the worst leaking vai e, fitting, or component and act the summation of the leakage of all valvt s, fittings, or components in that leakage path. ,yf4g Operatihg experience with the main steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness ) of the valves; therefore the special requirement for testing these valves. E h PERRY - UNIT 1 .B 3/4 6-1 Amendment No. A9/,35 1
PY-cerin a R-IS 76 L Altnehme.n+ 2 l'ay 5 of 7 Bases: Insert A Where a leakage path contains more than one valve, fitting, or component in series, the leakage for that path will be the minimum pattreay leakage and not the summation of the leakage of all valves, fittings, or components in that leakage path. The Type B and C leakage rates (and the secondary containment bypass leakage rate) are obtained from a sumation of the leakage rates (for each type of leakage) through all the applicable containment leakage paths. For these types of leakages, --,,.-r,r g e
j f' Y - C E.T /N R R - /5 74 L A th&of.2 \\ y CONTAINMENT SYSTEMS Puy_ g.f 7 l 3 BASES 3/a.6.1 CONTAINMENT (Continued) R e p l a c e. wMh g j Insert B i l } 3/4.6.1.2 CONTAINMENT LEAKAGE (Continued)g = 1 i ~ f The surveillance testing for measuring leakage rates is consistent witd A-the requirements of Appendix J to 10 CFR 50 with the exception of exemptions 4 (granted for testing the airlocks after each opening. j _3/4.6.1.3 CONTAINMENT AIR LOCKS 3 The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and l l the c0ntain ent leakage rate given in Specifications 3.6.1.1 and 3.6.1.2. l The specification makes allowances for the fact that there may be long periods of time when the air locks will be in a closed and secured position during reactor operation. Only one closed door in each air lock is required to main-j tain the integrity of the containment. f 1 i The air supply to the containment air lock and seal system is the service j and instrument air system. The system consists of two 100% capacity air l compressors per unit and can be cross-connected. This system is redundant l and extremely reliable and provides system pressure indication in the control l room. i 3 /a. 6.1. 4 MSIV LEAKAGE CONTROL SYSTEM i l Calculated doses resulting from the maximum leakage allowance for the f main steam line isolation valves in the postulated LOCA situations would be i 1 a small fraction of the 10 CFR 100 guidelines, provided the main steam line i system from the isolation valves up to and including the turbine condenser remains intact. Operating experience has indicated that degradation has i occasionally occurred in the leak tightness of the MSIV's such that the -{ specified leakage requirements have not always been maintained continuously. ~ 1 The requirement for the leakage control system will reduce the untreated leakage from the MSIV's when isolation of the primary system and containment is required. 3/4.6.1.5 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural. integrity of the containment will be maintained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 15 psig in the event of a LOCA. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability. QU .w l PERRY - UNIT 1 B 3/4 6-2 Amendment No.19 i .,. _.. - _ _... - -. - -, - -, _ -. _ _. _ _ - _ _ - ~
l ~ P Y-c E.Els!R R - 157 C L A hdmut 2 i 1 Bases: Insert B The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J to 10 CFR 50 with the exception of the following exemptions: a) Section III.D.2(b)(ii) - The air lock seal leakage test of Section III.D.2(b)(iii) of Appendix J may be substituted (following normal air lock door opening) for the full-pressure test provided that no maintenance has been performed that would affect the air locks sealing capability (Reference 1). b) Section III.A.5(b) - The design basis allowable leakage rate L (rather than the as-left acceptance criterion of 0.75 percent of L ), is designated as the value against which the as-found Type A test results are compared when scheduling for future periodic Type A tests in accordance with Section III.A.6 of Appendix J (Reference 2). i References (1) PNPP Safety Evaluation Report Supplement 7, Section 6.2.6 " Containment Leakage Testing", November 1985. (2) [ Exemption approval letter from the NRC.] I l 1 i i ,}}