ML19327B539
| ML19327B539 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/25/1989 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19327B538 | List: |
| References | |
| NUDOCS 8911010178 | |
| Download: ML19327B539 (10) | |
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f .. 1 ., l _ ' REFUELING OPERATIONS 3/4.0.4 CONTAINMENT BUILDING PENETRATIONS l, l' LIMITING CONDITION FOR OPERATION n \ , 3.9.4 The containment building penetrations shall be in the following status:
- a. The equipment hatch closed and held in place by a minimum of.four bolts, j b. A minimum of one door in each airlock is closed, and !
'c. Each penetration providing direct access'from the containment ;
atmosphere to the outside atmosphere shall be eithe.a: '
- 1) Closed by an isolation valve, blind flange, or manual valve, or ':
.2) Exhausting through an 0FERABLE Reactor. Building Containment Purge System HEPA filters and activated carbon adsorbers.
[ APPLICABILITY': Ouring CORE /u.TERATIONS or movement of irradiated fuel within
- the containment.
ACTION: With.the requirements of the above specification not satisfied, immediately {.. suspend all operations involving CORE ALTERATIONS or movement of irradiated fusi in the containment building. ; SURVEILLANCE REQUIREMENTS _ 4.9.4.1 Each of the above required containment building penetrations shall be determined to be either in its closed / isolated condition or exhausting through an OPERABLE Reactor Building Containmert Purge System ith th; ;;;;tility-e+- t ir.; at n i;;1'., i;;l;.ted _;;. h;;t;r '.ilur; within 72 hours prior to the ] start of and at least once per 7 days during CORE ALTERATIONS cr movement of I irradiated fuel in the containment building by: I
- a. Verifying the penetrations are in their closed / isolated condition, or I
- b. Verifying the upper and lower containment purge supply and exhaust valves close upon a High Relativa Humidity test signal.
( CATAWBA - UNITS 1 & 2 3/4 9-4 Amendment No (Unit 1) Amen:! ment Na (Unit 2) l
j '^ ,9 A o . . l-
~
- o. .
REFUEL.ING OPERATIONS SURVEft:JNCEREQUIREMENTS(Continued)
~4.9.4.2 The Reactor BuildindContainman'; Purge M;.dshall be demonstrated
[ OP5RA8LE: @ tar a4 LeweD (54sysigy j
- a. At least once per 31 days by initiating flow through the HEPA filters i and activated carbon adsorbers and verifying that the system operates l for at least 10 continuous hours with the heaters operating;
- b. At least once per 18 months or (1) after any structural maintenance j on the HEPA filter or activated carbon aosorber housings, or l l
(2) following painting, fire, or chemical release in any ventilation : zone communicating with the system by: i
- 1) Verifying that the cleanup system' satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedures guidance in Reguia-tory Positions C.5.a. C.5.c, and C.S.d* of Regulatory Guide 1.52.
Revision 2, Mar:h 1978, and the system. flow rate is'25,000 cfm t 10% (both exhaust fans operating); ,
- 2) Verifying within 31 days after removal, that a laboratory analysis of a representative activated carbon sample obtained l f3 in accore nce with Regulatory Position C.6.b of Regulatory
,/
Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 6%; and
- 3) Verifying a system flow rate of 25,000 cfm i 10% (both exhaust fans operating) during system operation when tested in accordance with ANSI H510-1980.
N.
- c. After every 720 hours of activated carbon adsorber operation, by l verifying, within 31 days after removal, that a laboratory analysis -
of a representative activated carbon sample obteined in accordance l with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Posi-tion C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 6%;
- d. At hast once per 18 months by:
- 1) Verifying that the pressure drop across the combined HEPA fil-ters, activated carbon adsorber banks, and prefilters is less l
than B inchas Water Gauge while operating the system at a flow rate of 25,000 cfm i 10% (both exhaust fans operating); and
'The requirement for reducing refiigerant concentration to 0.01 ppm may be satisfied by operating the system for 10 hours with heaters on and operating.
9 CATAWBA - UNITS 1 & 2 3/4 9-5 AmendmentNo.d(Unit 1) AmendmentNo.d(Unit 2)
w .y 7 :
+
- o '
REFUELING OPERATIONS f. SURVEILLANCE REQUIREMENTS (Continued) ,
- 2) ' Verifying that the filter train duct heater dissipates i 120
- 12 kW. .
- e. After each complete or partial replacement of : HEPA filter bank, by verifying that the cleanup system satisfies the in place penetration .;
and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a DOP test aerosol while operating the system at a flow rate of 25,000 cfm
- 10% (both exhaust fans operating); and
,' /. After each complete or partial replacement of an activated carbon f adsorber bank, by verifying that the cleanup system bank satisfies '
the in place penetration and bypass leakage testing accoptance cri-teria of less than 1% in accordance with ANSI N510-1980 for a halo-genated hydrocarbon refrigerant test gas while operating the system at a ficw rate of 25,000 cfm i 10% (both exhaust fans operating). i a l. 1 i CATAWBA - UNITS 1 & 2 3/4 9-6 AmendmentNo./(Unit 1) l AmendmentNo.J4(Unit 2)
y __ _ _ _._ _ _ _ . . _ _ . _ _ _ I!
'Q* ,.4- ,
T.n c or e. b b g w i ELING OPERATION 3 n !- . 6 ., b REFU SURVEILLANCE REQUIREkENTS-(Continued) , 3
, (p 4.9.4.g The Reactor Building "- ' '- j' ""-- '-^- shall be demonstrated OPERABLE:
fb 10 e i s ... t . =^ 3.% At least once per 18 months or (1) after any structural maintenance on the HEPA filter or activated carbon adsorber housings, or f. (2) following painting, fi i ical release in any ventilation r zone communicating with e, system b : wb
- 1) Verifying that tne system' satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test proce s guidance in Reguia-tory Positions C.5.a. C.5.c 5. af Regulato ide 1.52, Revision 2, March 1978, a theasyst f.1 .
rete i 30 cfm
- xt;;
210% (5 th . h:::t ' = m\;;; 1g
- 2) Verifying within 31 days after rem 7o ai, snat a laboratory analysis of a representative activated carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory j,
' ')
Guide 1.52 Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Positicr. C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 6%; and
. k
- 3) Verifying a system f1 rate ofl Dif 00 cfm i 10% (i:th =h:=0
'--- -- - - ' duri gas stem op ation when tested in accordance with ANSI N510-1980. A i After every 720 hours of a vated carbon adsorber operation, by p b f. verifying, within 31 days after removal, that a laboratory nalysis of a representative activated carbon sample obtained in acc.ordance. f with Regulatory Posit. ion C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Posi-tion C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 6%; _
G.M. Atleastonceper18monthsbf M Verifying that the pressure drop across t combined HEPA fil-
- ra ctivated srbon adsorber banks, an refilpers is less f Man JE nches Water Gauge while operating em at a flow 3.8 f$000 cfm i 10% (5 th =h:=t f=$he,sp:t' : :;_. ;'; *nd--
' ^ ' ^ ^ ^
2" Yh: 7yan ;'r::=t f;r md :ing r:f-i;;r=t :=::ntr:ti:r t: 0 01 ;;r 7:y 5:
- thf':d by ;;;nt'r.; tt: ;y:t:: fr 10 5 ; n eith h = t= = = d ;; a tin .
CATAWBA - UNITS 1 & 2 3/4 4 AmendmentNo./(Unit 1) _ Amendment _No./(Unit 2)
p , 1 > A, REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) [
'W T, t' rifyir.; th:t th: " it:r tr:f- 6 t hu t:r di ni;:tn 100 a 1; ;tJ.- -
- h. After each complete or partial replacement of a HEPA filter bank, by i verifying.that the cleanup system satisfies the in place penetration l and bypass leakage testing acceptance criteria of less than 1% in occa ce with ANSI N510-1 or a DOP test aerosol while operating J4 - :r__in;;; en at a flow rate ,300 cfm t 10% 0;th nh=:t in:
1 and 4,f. After each complete or partial replacement of an activated carbon f, adsorber bank, by verifying that the cleanup system bank satisfies the in-place penetration and bypass leakage testing acceptance cri-teria of less than 1% in accordance with ANSI N510-1980 ~N ~ genated hydrocarb at a flow rate of efrigerant test gas while operating
, 00 cfm i 10%
tem FMj,l i- r l' (
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i i I l' ) 1 I I l i l 1' l 1: l ; 1 CATAWBA - UNITS 1 & 2 3/4 6b Amendment No. Unit 1) Amendment No. Unit 2) l
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, s i F DISCUSSION. NO SIGNIFICANT HAZARDS ANALYSIS
- - AND ENVIRONMENTAL IMPACT STATEMENT The proposed Technical Specification amendment would 1) Delete a statement from Surveillance Requirement 4.9.4.1 concerning the capability of the ;
incore inttrumentation. room automatically isolating upon heater failure;
- 2) Add a clarification to Surveillance Requirement 4.9.4.2; and 3) Add Surveillance Requirements for the Incore Instrumentation Room Purge Subsystem. ,
Technical Specification 3/4.9.4 provides Limiting Conditiona for Operation (LCO) and Surveillance Requirements for Containment Building Penetrations. H This Specification is applicable during core alterations or movement of irradiated fuel within the containment. LCO 3.9.4c requires that each penetration which provides direct access to the oucside atmosphere be isolated or exhausting through REPA filters and carbon adsorbers. , The Containment-Purge (VP) System provides a means of ventilating upper and lower Containment as vall as the Incore Instrumentation Room (ITR) through cleanup filters prior to discharge to atmosphere through the unit vent. The VP System is designed to sufficiently reduce airborne radioactive materials inside Containment to levels suitable for personnel access. The supply portion of the VP System consists of two 50 percent capacity fars for Containment and one 100 percent capacity fan for the IIR. The exhaust portion also consists of two 50 percent capacity fans for Containment and one 100 percent capacity fan for the IIR. As each exhaust Ian is started, the correspondinB supply fan starts automatically. During Containment purge operation, purge exhaust heaters are automatically staged on as necessary to maintain the relative humidity of the air through the Containment purge exhaust filters below approximately 70 percent. The IIR Purge subsystem design does not include filter heaters. The IIR Purge subsystem does not require heaters because it does not perform its function in the vicinity of refueling activities. A fuel handing accident has been analyzed assuming the Containment Purgo System is in operation during refueling operations. This analysis is described in Section 15.7.4 of the Catawba FSt.R and it accounts for heaters not being installed in the IIR Purge subsystem. On May 15, 1989, while Unit 1 was in Mode 1, Power Operation, and Unit 2 was in Mode 5 Cold Shutdown, Operations personnel were reviewing PT/1/A/4450/01, Containment Purge Periodic Test. They discovered that if this procedure was performed during core alterations cr movement of irradiated fuel in Containment, a possible violation of the intent of Tech Spec Surveillance Requirement 4.9.4.1 could occur due to operating the IIR Purge subsystem without the capacity to automatically isolate the system upon high humidity. At this time, Operationa personnel initiated Problem Investigation Report 0-C89-0198. On June 5, 19b9 Design Engineering evaluated the Tech Spec and concluded that heaters are not required for
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operability of the IIR Purge subsystem, and Tech Spec Surveillance ' Requirements 4.9.4.1 and 4.9.4.2 do not apply to the IIR Purge subsystem. Tech Spec 3.9.4 LCO applies to the IIR Purge subsystem. Ilowever, there are net associated Tech Spec Surveillance Requirements which verify operability of this subsystem. On June 19, 1989 voluntary LER 413/89-09 was issued addressing this event. The deletion of the phrase "with the capability of being automatically isolated upon heater failure" will add clarity to Survoillance 4.9.4.1 and is meant to show that it is applicable to the IIR Purge subsystem. Deletion of this phrase will not make this Surveillance any less restrictive since Surveillance 4.9.4.lb. requires checking the operability of the high humidity isolation capability of the VP System. The proposed change to Surveillance Requirement 4.9.4.2 specifies that the Reactor Building Upper and Lower Containment Purge Subsystems shall be demonstrated operable. The change is intended to eliminate confusion regarding which subsvstem is to be demonstrated operable. The proposed change will not make this Surveillance any less restrictive. Proposed Surveillance 4.9.4.3 would add specific requirements for the IIR Purge subsystem. These requirements are sinilar to those currently required fer the VP System filter trains modified with IIR Purge subsystem specific numbers. The Surveillance Requirement 4.9.4.2.a. which requires 10 continuous hours of testing with the heaters operating, is not applicable to the IIR Purge Subsystem and is not included in the proposed 4.9.4.3 surveillance. It should be noted that the proposed 4.9.4.3 surveillance adds requirements to the Tech Specs which would verify operability of the IIR Purge subsystem. l 10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the proposed amendment would not: (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of saiety. The proposed amendment does not involve an increase in the probability or consequences of any previously evaluated accident. The design and operation of the plant will not be affected by these proposed changes. The modification to Surveillance 4.9.4.1 would expand this Surveillance to cover the IIR Purge subsystem without deleting any current requiremants on the VP System. The addition of Surveillance Requirement 4.9.4.3 would add requirements for the IIR Purge subsystem which are not currently contained in Tech Specs.
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~ ,pa, The proposed changes v111'not create the possibility of a new or different
[- kind of accident from any accident previously evaluated. The proposed amendment would add requirements to the IIR Purge subsystem which do not currently exist in the Tech Specs. The changes will not allow the plant to be operated in a mant.er different than currently allowed. r The proposed amendment will not reduce any margin cf safety. The proposed
- changes will add requirements for the IIR Purge Subsystem which are not
' currently contained in the Tech Specs.
, The Commission has provided several examples of license amendments which would not involve significant hazards considerations (48 FR 14870). One of the examples listed was example (ii), "A change that constitutes an i additional limitation, restriction, or control not presently included in the technical specifications: for example, a more stringent surveillance requirement." This amendment is similar to example (ii). 3- For all the above reasons, Duke Power concludes that this proposed amendment does not involve any significant hazards considerations. ENVIRONMENTAL IMPACT The proposed Technical Specification change has been reviewed against the criteria of 10 CFR 51.22 for the onvironmental considerations. As shown above, the proposed change does not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released offsite, nor increase individuc1 or cumulative occupational radiation exposures. Based on this, the proposed Technical Specification change meets the criteria given in 10 CFR 51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement. t e P}}