ML18046A719

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Forwards Draft Evaluation of SEP Topic VI-4, Containment Isolation Sys. Requests Advice If as-built Facility Differs from Current Licensing Basis.Requests Defined Basis Upon Which Specific Isolation Configurations Were Approved
ML18046A719
Person / Time
Site: Palisades Entergy icon.png
Issue date: 06/09/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Hoffman D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
TASK-06-04, TASK-6-4, TASK-RR LSO5-81-06-023, LSO5-81-6-23, NUDOCS 8106160646
Download: ML18046A719 (47)
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~ Docket No. 50-255 LS05 06-023 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 1945 W Parnall Road Jackson, Mich1gan 49201

Dear Mr. Hoffman:

June 9, 1981 'i-

SUBJECT:

FORWARDING DRAFT EVALUATION REPORT OR SEP TOPiC VI-4, -.. CONTAINMENT ISOLATION SYSTEM FOR THE PALISADES NUCLEAR POWER PLANT Enclosed is a _copy of our draft ev~luation of SEP Topic VI-4, Containment Isolation System. This assessment compares your facility, as described in Docket No. 50-255,.with the criteria currently used by the regulatory st_aff for licensing new facilitie$. *Please infonn.us if your as-built facility differs from the licensing basis assumed in our assessment. ~0'. In a~d1~~9/'1, I would 11 ke to draw. your at tent.ion to two of the m9re significant issues cont91ned 1n conclusion, location of both isolation valves outside cont~inment and use_of a simple check as an isolation valve outside containment. Both-of these'items appear to contradict the explic1t wording of the regulations and.no other acceptable defined basis coljld-be detennined from the 1nfonnat1on provided. To enable-us-to perfonn our assessment of the deviations identified in -this report, we will need the defiiled basis upon which *the specific isolation configurations at the Palis.CAdes Plant were judged to be accept-ab1 e by you. Please provide this 1nfonnat1on as. a. part of your comments -Of1 *thiS rer>ort. Cormnents are required within 30 days of receipt of this let_ter so that _they. may be 1nclud!d.in* our final report. This evaluation will be a_ basJc* J.npLft to.the integrated safety assessment for y9ur facility unless YOl.f idilnti.fy changes needed to reflect the as-built co~ditions <lt. your _OFFIC_E. * *****************: **************.******* **************.. ******** ********************* ******'-***************...................... -'........................ lSURNAME. ~.................. *...................... DATE~, *........................................._....................... ********************** **-******************* ****************** ****,************** ******. NRC FORM 318 11f)J80l NRCM f)24f) Cff lCIAL. RECCR.C CCPY ,-, USGPO* t98~329*8:l4

~, -~- ii!; ---- - fac11 i ty. This assessment may be revised in the future if your fac 11 i ty design is changed or if NRC criteria relating to this subject are modified before the i)ill:~9rated assessment is completed. \\-:* *r.. Er;iclosu~: Draft SEP Top1c VI-4 cc w/enclosure: See ndf~~ page Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing (*See previous yellow for additional concurrences.) ,-c: *<<,,,_._ ** ,:::::~ *

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~, Docket No. 50-255 LS05*81-Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 1945 W Parnall Road Jackson, Michigan 49201

Dear Mr. Hoffman:

SUBJECT:

FORWARDING DRAFT EVALUATION REPORT OF SEP TOPIC VI-4, CONTAINMENT ISOLATION SYSTEM FOR THE PALISADES NUCLEAR POWER PLANT .Enclosed is a copy of our draft evaluation of SEP Topic VI-4, Containment Isolation System. This assessment compares your facility, as described in Uocket No. 50-255, with the criteria currently used by the regulatory staff for licensing new facilities. Plea~e inform us if your as-built

  • facility differs from the licensing basis assumed in our* assessment.

In addition, I would like to draw your attention to two of the more significant 1Ssues contained in conclusion, location of both isolation.

  • valves. outside containment and use of a simple check as an isolation valve outside ~ontainment *. Both of these items appear to contradict the explicit word-ing *Of. the regulations and no other acceptable defined basis could he detenn1ned from t.h_e infonnat1on provided.

Conunents are required within 30 days of receipt of this letter so that they may be included* in our f:!nal report. This evaluation wil.l be. a,.. basic input to the integrated safety assessment for your facility unless you* identify ch~nges needed to reflect the as-bu1l-t* conditions at-.your facility. This*assessment may be revised in the future if your facility design 1s changed or if NRC criteria relating to this subject are.modified before the in:t'.egrated assessf!IE!nt 1S completed. Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch. No. 5 Division of Licensing ORB#5:DL:C AD:SA:DL Enclosure.: DCrutchfield GLainas Draft SEP To ic VI-4 5/ /81 5/ /81 I

Mr. *David P. Hoffman I UNITED STATES NUC AR REGULATORY COMMISSION WASHINGTON. 0. C. 20555 June 9, 1981 Nuclear Licensing Administrat6r Consumers Power Company 1945 W Parnall Road Jackson, Michigan 49201

Dear Mr. Hoffman:

SUBJECT:

FORWARDING DRAFT EVALUATION REPORT OF SEP TOPIC VI-4, CONTAINMENT ISOLATION SYSTEM FOR THE PALISADES NUCLEAR POWER PLANT Enclosed.is a copy of our draft evaluation of SEP Topic Vl-4, Containment Isolation System. This assessment compares your facility, as described in Docket No. 50-.255, with the. criteria-currently used by the regulatory staff for licensing new facilities. Please inform us if your as-built facility differs from the licensing basis assumed in our assessment. In addition, I would like to draw your attention to two of the more significant.issues contained in conclusion, location of both isolation valves outside containment and use of a simple check as an isolation valve outside containme_nt. Both of these items appear to contradict the explicit wording of the regulations and no.other acceptable defined basis could be determined from the information provided. To enable us to perform our assessment of the deviations identified in this report, we will need the defined basis upon which the specific isolation configurations at the Palisad.es PJant were judged to be accept-able by you. *Please provide this information as a part of your comments on this report. Comments are required within 30 days of receipt of this letter so that they may be included in our final report. This evaluation will be a basic input to the integrated safety assessment for.your facility unless you identify changes needed to reflect the as-built. conditions at your

.) facility. This assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this subject are modified before the integrated assessment is completed.

Enclosure:

Draft SEP Topic VI-4 cc w/encl osure: See next page I Sincerely, L 7?1 l!w:/;IL/,/ Dennis M. Crutchfield,~ Operating Reactors Branch No. 5 Division of Licensing

i I

    • ~.

I Mr. David P. Hoffman cc M

  • I. M i 11 e r, E sq u i re Isham, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670 Mr. Paul A. Perry, Secretary Consumers Power Corrpany 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Corrpany 212 West Michigan Avenue Jack son, Mi chi ga n 49201 Myron M. Cherry, Esquire Suite 4501 One IBM Plaza Chicago, Illinois 60611 Ms. Mary P. Sinclair Great Lakes Energy Alliance 5711 Summerset Ori ve Midland, Michigan 48640 Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006 Township Supervisor Covert Township Route.l, Box 10 Van Buren County, Michigan Office of the Governor (2)

Room 1 - Capitol Building Lansing, Michigan 48913 49043 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460) U. S. Environ.mental Protection Agency Washington, D. c. 20460

e.

U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATTN: EIS COORDINATOR 230 South Dearborn Street Chicago, Illinois 60604 Charles Bechhoefer, Esq., Chairman Atomic Safety and licensing Board Panel

  • U. S. Nuclear Regulatory Conmission Washington, D. C.

20555 Dr. George C. Anderson Department of Oceanography University of Washington Seattle, Washington 98195 Dr. M. Stanley Livingston 1005 Calle La~go

  • Santa Fe, New Mexico 87501 Resident Inspector c/o U. S. NRC P. O. Box 87 South Haven, Michigan 49090 Palisades Plant ATTN:

Robert W. Montross Plant Manager Covert, Michigan 49043 William J. Scanlon, Esquire 2034 Pauline Boule~ard Ann Arbor, *Michigan 48103

e 1Containment Systems Branch £valuation Report on SEP Topic VI-4, Containment Isolation System for the Palisades Nuclear Plant, Unit l Docket No. 50~255 I Introduction The Palisades Nuclear Power Plant, Unit l began corranercial operation in 1971. Since then safety review criteria have changed. As part of the Systematic Evaluation Program (SEP), the containment isolation system for the Palisades plant has been re-evaluated. The purpose of this evalu-ation is to document the deviations from current safety criteria as they relate to the containment isolation system. The significance of the identified deviations, and recommended corrective measures to improve safety, wi 11 be the subject of a subsequent, inte.grated assessment of the Palisades plant.* The safety criteria used in the. ~rrent eval uatfon of the containment isolation system for the Palisades plant are contained fn ttiP. following references:.

1) 10 CFR Part 50,,Appendix A,, General Design Criteria for Nuclear Power Plants (GDC 54, 55, 56 and 57).
2)

NUREG 75/087, Standard Review Plan for the Review of Safety Analy-sfs Reports for Nuclear Power Plants (SRP 6.2.4; Containment Iso-iation System).

3)

Regulatory Guide L11, Instrument Lines Penetrating Primary P.eactor

  • Containment.

ENCLOSURE

4)

Regulatory Guide 1.141, Revfsion.1_, Containment Isolation Provisions for Fluid Systems. I I I. Related Safety Topi cs In order to avoid duplication of effort the review areas identified below are not covered in this report since they will be reviewed under other topics or ongoing generic reviews. However, they are related and.essential to the completion of the re-evaluation of the containment isolation system for the Palisades plant. They a re: (1) III-1, Classification of Structures, Components and Systems (Seismic and Quality) (2) 111-4.C, Intemall,y Generated Missiles (3) III-5.A, Effects of Pipe Break on Structures, Systems and Components Inside Containment (4) III.;.S.B, Pipe Break Outside Containment*

  • cs) lI l-6 t (6) III-12, (7) VI-6 1 (8) VII-2, Seismic Design Considerations.

Environmental Qualification of Safety Related Equipment Containment Leak Testing Engineered Safety Feature System Control Logic and Design (9) VIII-2, Onsite Emergency Power. Systems - 'Diesel Generator (10) VIII-4, Electrical Penetrations of Reactor Containment (11) NUREG-0737, Clarification of TM! Action Plan.Requirements, Item II.E.4.2, Containment Isolation Dependability (12) NUREG-0660, NRC Action Plan Developed as a Result of the TMI-2 Accident, Item II.E.4.4., Containment Purging and Venting Requirements

~'

  • ~".I*.

IV Review Guidelines The containment isolation syste~ of~ nuclear power o1ant is an engineere~ safety feature that functions to a11o~ the normal or emergency.passage of fluids through the containment boundary whfle preserving the ahil ity of the boundary to prevent or limit the escape of fission products to the environs that may result from postulated accidents. General Design Criteria 54, 55_, 56, and 57 of Appendix A to 10 CfR Part 50 pertain to the containment iso-lation system of a nuclear power plant. General Design Criterion 54.establishes design and test requirements for the leak detection provisions. the isolation function and the containment capabiMty of the isolaHon barriers in lines penetrating the primary re-actor containment. From the standpoint of containment isolation, leak de-tection provisions should be capable of quickly detecting and responding to a spectrum of postulated pipe break accident conditions. To accomplish ' this, diverse parameters should be monitored to initiate the containment isolation function. The parameters selected should assure a positive, rapid response to the developing accident condition.* This.aspect of the containment isolation system review will be addressed during the review of. the post-TM! requirements approved for implementation, as stated in NUREG-0737 at Item II.E.4.2. Leak detection capability should also be provided at the system level to alert the operator of the need to isolate a system trai.n equipped with re-mote manual isolation valves. SRP 6.2.4,. at Item II.11, provides guidance in this regard.

    • With respect to the design requirements for the isolation function, all non-essential systems should be automatically isolated (with manual valves sealed closed)~ and valve closure times should be selected to assure rapid isola.tion of the containment in the event* of an accident.

The review of the classification of systems as essential or non-essential, and the auto-matic is.olation provisions for non-essential systems by appropriate signals, will be addressed in conjunction with.the review of the post-TM!.requfre-ments as stated in NUREG-0737 at Item II.E.4.2. The closure time of the '\\ containment ventilation system isolatfon valves will be evaluated in con*- . junction with the ongoing generic review of purging practices at operating* plants (see NUREG~0660 at Item II.E.4.4). The electrical power supply, instrumentation and control systems should be designed to engineered safety feature criteria to assure accomplishment, of the containment isolation function. This aspect of the review is covered under SEP Topics VII-2 and VIII-2. Also, resetting the isolation signal should not result in the automatic re~opening of containment isolation va.lves. This will be addressed in conjunction with the.review of the post-TMI *requirements approved for implemen~ation, as stated in NU~EG-0737,_ at* I tern I I. E. 4. 2. With respect to the capabilities of containment isolation barriers in* lines penetrating primary containment, th.e isolation.barrier.s shouldbe designed

  • to engineered safety feature criteria, and protected against missiles, pipe.

whip.and jet impingement. Typical isolation barriers foclude valves, closed . systems and blind flanges.. Furthermore, provisions should be made to permit periodic leak testing of the isolation barriers.

~' ~_. - 5 The adequacy of the missile, pipe whip ~nd jet impingement protection will be covered under SEP Topics III-4.C, III-5.A and III-5.B. The ac-ceptability of the design criteria originally used in the design of the containment isolation ~ysiem components will. be covered in SEP Topics III-1, III-6 and III-12. The adequacy of the leak testing program wili be covered under SEP Topic VI-6. The acceptability of electrical penetrations will be covered in SEP Topic VIII-4. General Design Criterir. 55. 56 and 57 establish explicit requirements for isolation valving in lines penetrating the containment. Specifically. they *address the numl:>er end location of fsolation valves (e.g ** redunc'ant valving with one located inside containment an~ the ot~er located Qutside co'nta foment), valve actuation prov is ions (e.g., a.utomati c or remotP manual isolation valves), valve position (e.g;, loc~ed closed~ or the position of

  • greater safety in the event of an accident or power failure). and valv~ type (e.g., a simple check valve is not a* pennissable automatic isolation. valve out~.

side containment). Figures 1 and 2 depict the *explicit valve arrangements spe* cified in GDC 55 and 56, and 6DC 57, respectively. 'Goe 55 and 56 also pennit containment isolation provisions for lines pene- . trat ing the primary conta i nmen~ boundary that di ff er from the exp1i cit re-. quirements, provided the basis for acceptability is defined. Tnis provi~o is typically invoked when establishing the containment isolation* require-I ments for essential (f.e., safety related) systems, or there is 1 clear im-provement in safety. -..-*----*~ -.. -~ *---*-----*-*-----*- -- -*

6 - \\ Standard Review Plan 6.2.4 at Item 11.3 presents guideline~ for acceptable alternate containment isolation provisions ~or certain classes of lines. Containment isolation provisions that are found acceptable on the "other defined basis" represent confonnance ~ith the GDC and do not const;tute ex.ceptions. The following evaluation addresses deviations in the containment isolation provisions from the explicit requirem~nts of the General Design Cr.iteria.

.e GENERAL DESIGN CRITERIA 55 AND 56 ISOLATION VALVE CRITERIA MISSILE PROTECTION INSIDE OUTSIDE CONTAINMENT INSIDE

  • OUTSIDE SEALED CLOSED
  • 4 SEALED CLOSED

~- 0 . /:).. ~ 6 't> 0.

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~ ~ *<l AUTOMATIC SEALED CLOSED ~.. <l .6. OR AUTOMATIC AUTOMATIC AUTOMATIC OR ~ c:I Figure 1

~.. GENERAL DESIGN CRITERION 57 ISOLATION VALVE CRITERIA MISSILE PROTECTION INSIDE OUTSIDE CONTAINMENT INSIDE OUTSIDE .~.. 4. AUTOMATIC OR REMOTE MANUAL . o"o ~ AUTOMATIC '.. d OR ~LOSED SYSTEM . 0 p . *. o REMOTE MANUAL. d".. ~* CLOSED SYSTEM Figure 2. 0 o:. t>. ... 0 ~. .. 0 SEALED CLOSED ~

  • 4 SEALED CLOS ED

. 6. /

. V. EVALUATION The containment isolat'ion provisions for the lines penetrating the primary reactor containment of the Palisades Nuclear.Power Plant, Unit l are tabulated in Tab~e l. This infonnation was obtained from the documents referenced in Section VII. There was insufficient infonnation to complete Table l; there-fore, the licensee should provide the missing infonnation, and make any neces-sary corrections. . The containment isolation provisions, as tabulated in Table 1, were evaluated against the requirements of General Design Criteria (GDC.) 54, 55, 56 and 57 (Appen~ix A to 10 CFR Part 50), and the supplementary guidan.ce of Standard Re.- view Plan (SRP) 6.2.4 (Containment Isolation System), where applicable. De.vi-ations from the explicit requirements of GDC 54, 55, 56 and 57, and the accept-ance criteria. of SRP 6.2.4 are tabulated* in Table 2. Tab1e l gives the licensee's penetration class designation for ma*ny of ~he lines penetrating containment. The isolation valve arrangements for these penetra-

  • ti on _classes are shown in Figures 3 and 4.

The figures were obtained from Reference 8. Following are evaluations of these penetration classes against GDC 55, 56 and 57.

  • Penetration Class Al Penetration Class Al s*hows influent and effluent lines open to the containment with two isolation valves in series outside c*ontaim:nent.*. GDC 56 applies to the lines* in Penetration Class Al.
  • GDC 56 specifies that one valve should be lo-cated inside containment and one valve should *be located outside containment.

Consequently, the isolation valving arrangement for Penetration Class Al d-iffers from the explicit requirements of GDC 56 from the standpoint of valve location. Locating both containment isolation valves outside ~ontainment may be acceptable if the criteria used in the design of the piping between the containment and the first valve are sufficiently conservative to provide adequate assuranc~ of integrity. The following containment penetrations are included in Penetration Class Al: 1, 4, 4a, 52 and 68. Penetration Class A2 Penetration Class A2 shows three isolation configurations that are open to the containment. GDC 56 applies to the lin~s in Penetration Class A2. One of the isolation configurations (i.e., the line having a locked-closed valve inside containment and a locked-closed valve outside containment) satisfies the explicit requirements of GDC 56._ The following containment penetrations have this isola-tion configuration in Penetration Class A2: 64, 66 and 72. The isolation configuration having a blind flange inside containment and a locked closed valve outside containment differs from the explicit requirements of GDC 56 .from the standpoint of isolation barrier type. GDC 56 does not address the use of blind flanges. However, a blind flange is an acceptable isolation barrier in liieu of a valve. The basis for this appears in SRP 6.2.4 at Item a;3. Also, the locked-closed valve could be an automatic isolation valve and still satisfy GDC 56. The following containment penetrations have this isolation*configufation in Penetration Class A2: 18 and 27. With regard to penetration 27, there is insufficient infonnation about the ad~ ministrative control exercised over the power operated valve outside containment. Since the associated line (ILRT fill line) is a non-essential line, and would not be used during plant operating modes 1, 2, 3 and 4. there should be *adequate --~*** ~-*.***\\" ___,__ **~.~ - .-:4*........... ~.....

  • 11 -

administrative control to assure that,the valve cannot be inadvertently opened; i.e., the valve should be a sealed closed isolation valve in accordance with the guidelines of SRP 6.2.4, at Item II.3. The isolation configuratiori having both a locked closed valve and a simple check valve outside containment differs from the explicit requirements of GDC 56 from *

  • the standpoint of valve location and valve type.

GDC 56 specifie~ that one valve. should be located inside containment and one. valve should be located outside con-tainment, and that a simple check valve *may not be used as an automatic isolation valve outside containment. For this configurati6n to be acceptable, :the che_ck valve should be located insid.e containmel'\\t* Also, the locked closed va1ve could*. be_ an_ automatic isolation valve to satisfy GDC 56. The following containment penetrations have the above isolation config.urat.ion in Penetration Class A2.: 10, 30, 31 and 65. A judgment regarding the acceptability of -the simple. check valve.outside containment.as -a bona.fide containmen.t isoiafion valve will be.made in c6njunction with the.integrated assessment of the plant. With regard* to penetrations 30 and 31 (containment spray pump discharge lines), the actuation provisions for the.power operated valves CV-3001 (penetration 30) and CV-3002 (penetration 31) differ from the explicit requirements of GDC 56 in' that they are remote manual isolation valves.* Remote manual isolation valyes are .~ I provided iri lieu of automatic isolation valves because the lines, which are part

  • d of the containment spray system, have a post-accident safety.function (depres:..

suri za(i on. of the containment following a pipe break acci den~) which nece*ssi tate*s their being opened in.the event of an accident. Consequently, automatic isola-tion of thes~ lines is not appropriate. However, the capability does exist to remote manually isolate these lines if the need to do so should arise. The actuation provisions for these valves are acceptable based on the guidelines of SRP 6.2.4, at Item II.3. With regard to penetration 65 (instrument air line), the actuation prqvisions for valve CV 1211 differ from the explicit requirements of GDC 56 in that the valve is not automatically isolated. Valve CV 1211 should be automatically iso-lated, or justification for the instrument air line being an essential line should be provided. Penetration Class Bl Penetration Class Bl shows two series isolation valves outside containment in a line coming from the reactor coolant system. As shown, one of the valves. is an automatic isolation valve and the other is a nonnally open, manual valve. Dependin~ on the line, however, a simple check valve or remote manual valve is

  • used.*

GDC 55* applies to the lines in Penetration Class Bl.* GDC 55 specifies .that one valve should be located inside containment and one valve should be

  • located outside containment, with the valves being either locked closed or auto-.

matic isolation valves. The isolation v.alving arrangement for Penetration Class Bl, therefore, *differs from.the explicit requirements of GDC 55 from* the standpoint of valve location type, and actuation. Locating both isolation valves outside *containment may be acceptable if piping and valve design criteria are sufficiently conservative to preclude a breach of integrity. This matter is discussed under SEP Topic III-1. The use of a locil manual valve fof containment isolation is not acceptable, and

  • should be upgraded to an automatic isolation Yalve.

The following containment penetrations are included in Penetration Class Bl:

  • 36, 40 and 45.

For penetration 36, the parallel, remote manual, power operated valves, CV 2012 and CV 2022, should be provided with automatic actuation cap.a-bility. For penetration 45, the simple check valve outside containment is an /.*

\\...... :..

_ 13 -

.inappropriate automatic isolation valve; a'judgment regarding its acceptability will be made in conjunction with the integrated assessment of the plant.. Also, valve CV 2111 should be automatically isolated. Penetration Class 82 Penetration Class B2 shows a locked closed valve inside containment and a locked closed valve outside containment in a reactor coolant system effluent line. GDC 55 applies to the lines in Penetration_ Class 82. The isolation arrangement satisfies the explicit requirements of GDC 55. The following containment penetrations are included in Penetration Class 82:

35.

Penetration 35 shows two relief valves (RV 3164 and RV 0401), located between the two series isolation valves inside containment, which relieve to the contain~ ment. Consequently, the relief valves also have a containment isolation function in the reverse flow direction. Penetration Class Cl Penetration Class Cl shows two. types of valve arrangements for closed systems in-side containment that are missile protected, namely, a single simple check valve outside containment for influent lines and a single automatic isolation valve outside containment for effluent lines. GDC 57 applies to the lines in Penetra-tion Class Cl. GDC 57 specifies that a single automatic, remote manual or locked closed isolation valve outside containment is acceptable, but a simple chepk valve.is not an acceptable automatic isolation. valve.. The isolation valve ar* rangement having a single simple check valve outside containment differs from the explicit requirements of GDC 57 from the standpoint of valve type. / The following containment penetrations are included in Penetration Class Cl: 2, 3, 7, 8, 16 and 55.

For penetrations 7 -and 8, the main feedwater isolation valves {18"-N218R-0702 and 18"'-N218R-0701, respectively) should be power operated~ automatic isolation valves. In this regard, a power operated stop check valve would be acceptable. Penetration Class C2 Penetration Class C2 shows isolation valve arrangements for influent and efflu-ent lines of clos~d systems inside containment that are not missile protected. - The valve arrangements consist of two valves in series, outside containment. GDC 56 applies to the lines in Penetration Class C2. GDC 56 sp~cifies that on~ automaiic or locked closed valv~ should-be located inside containment and -one such valve ~hould be* located outside cor;tainment; also, a simple check valve may not be used as an automatic isolation valve outside containment.

  • The valve arrangements of Penetration.Class C2 differ from the_ explicit require-ments of GDC ~6 from the standpoint of valve location and.valvetype. All valve -

arrangements would satisfy the explicit requirements of _GDC 56 if one valve was located inside containment, particularly the simple check valve. GDC 56 permits isolation valve arrangements that differ from the explicit re-

  • qui rements provided the basis for acceptabi 1 i ty is defined. With. respect to Penetration Class C2, then, locating both isolation valves outside tont~inment may be acceptable since missile protection is not provided i~sfde containment.

The acc~ptabil i ty of this. is contingent on the criteria used in the design of the piping between the containment and first valve, and the first valve, which must provide adequate assurance of integrity. The following containment penetrations are included in Penetration Class C2: 5, 6 1 11, 14, 15, 25, 26, 37, 38, 39, 41, 42, 44, 46, 47, 49, 67 and 69~

l - 15 _. For penetrations 11, 14, Z6, J7, J9, 41, 42 and 67, the simple check valve is not an appropriate automatic isolation valve outside containment. A power operated automatic isolation valve would be acceptable. However, a judgment decision re-garding the acceptability of the simple check valve will be made at the time of the integrated assessment of the plant. Penetration 25 shows a capped test con-nection which should.be equip.ped with two locked closed isolation valves in series.* Penetration 44 shows a manual isolation valve (3/4 11-2084) which is not depicted by the isolation valve arrangements of Penetration Class C2, and which differs from the explicit requirements of GDC 56 from the standpoint of valve actuation; the subject valve should be a power operated valve that is a~tomatically actuated. Penetration Class.CJ

  • Penetration Class CJ shows two, locked tlosed isolation valves in series, outside containment, for effluent lines from systems that are closed inside containment and not missile protected.

GDC 56 applies to the lines in Penetration Class CJ. The valve arrang~ment described above differs.from the expliCit requirements of GDC 56 from.the standpoint of valve location, namely, ~ne valve should be lo-cated inside containment *. However, locating both valves ou_tside containment may be acceptable, based on*the discussion under Penetration Class.C2. The following containment penetrations are included in, Penetratipn Class CJ: JJ and 40A. Th*e following discussion pertains to those containment penetrations not covered by the Penetration Classes discussed above. a) Penet~ations 9, 20, 21, 24, 29~ 34, 4J, 56, 57, 58, 59, 60, 61, 62, £J, 70, 71 and 7J:

-~ *.; These containment penetrations are spares. Of these, penetrations 21, 29 and 73 show pipe caps and blind flanges being used as isolation barriers. Threaded and/or tack welded pipe caps, and blind flanges without leak test-ing provisions, are not suitable isolation barriers. b) Penetrations 12 and 13: Thesecontainment penetrations satisfy the explicit requirements of GDC 56,. and are acceptable. However, with respect to the test, vent and drain lines, pipe caps are not suitable isolation barriers; two locked closed isolation valves in series should be provided for these lines. Also, the flow. element located between the isolation valves at penetration _13 should be moved downst.ream*of the outboard isolation valves, or the licensee. should justify that the flow element is an acceptable isolation barrier. c)' Penetrations 17 and 48: These two containment penetrations serve the coritainmentpressure instru-mentation (8 lines).* Since signals for the actuation 9f engineered safetY features are derived from this instrumentation, it is impera~ive.that these li.nes be open and remain* open. Consequently, power operat~d valves, which could potentially spuriously close, are not provided in these lines. The instrument lines, however, are provided with test connections that are only capped. Again, pipe caps are not suitable isolation barriers; two locked closed isolation valves in series should be provided in e~ch test 1 ine. d) Penetrations 19, 50 and 51: / These containment penetrations are the* personnel air lock, emergency access air lock and equipment hatch, respectively. Several lines are associated with these penetrations that are equipped* only with pipe caps for isolation bar-riers. Pipe caps are not suitable isolation barriers and should be replaced with locked closed manual valves or blind flanges that are leak testable. e) Penetrations 22, 23 and 32: These containment penetrations *(safety injection) satisfy the explicit requirements of GDC 55 and are acceptable. f) Penetration 28: This penetration uses pipe caps outside containment as isolation barriers, which are not suitable isolation barriers. They should be replaced with locked closed manual valves or blind flanges that are leak testable. g) Penetrations 53 and 54: These penetrations are the two, emergency sump recirculation lines. The containment sump suction lines are part of the emergency core cooling system and the containment heat removal system, and must be opened follow-ing a loss-of-coolant accident to satisfy their post-accident functional

  • requirement, which is to pennit long tenn cooling of the reactor core and the containment atmosphere.

As a result, automatic isolation of these. lines is not acceptable and remote manual isolatio~*valves are provided. For this application, a single isolation valve is provided in each line since system reliability would be greater with only one isolation valve in the line. Also, the isolation valve is located outside containment since it is not practical to locate a second valve inside containment ~here it would /, be submerged following a loss-of-coolant accident. The emergency core cool- . ing system, which is a closed engine~red safety feat1..'re grade system out-side containment, serves as the second. containment isolation barri_er. The

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