ML19242B585
| ML19242B585 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/09/1979 |
| From: | Satterfield R Office of Nuclear Reactor Regulation |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7908090037 | |
| Download: ML19242B585 (8) | |
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fDTRIBUTION:
KENTRAL FILES I
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MEMORANDUM FOR:
J. Stolz, Chief. Light Water Reactors Branch 1. DPM FROM:
R. M. Satterfield, Chief Instrumentation and Control Systems Branch, DSS
SUBJECT:
ACCEPTANCE REVIEW 0F FSAR FOR CATAWBA NUCLEAR STATION I
l Plant Name:
Catawba Nuclear Station Docket Nos:
50-:13/414 j
Licensing Stage:
Milestone No:
22-01 I
Responsible Branch:
LWR-1 l
& Project V.anager:
H. Silver Systems Safety Branch Involved:
Instrumentation ar;d Control Systems ICSB Reviewer:
R. Stevens Requested Completion Date:
May 4, 1979 j
Review Status:
Complete i
The Instrumentation and Control Systems Branch has completed the Acceptance f
Review of Catawba Nuclear Station and provides the enclosed Acceptance i
Review Report. We have reviewed relevant portions of Chapter 1, 3 and 7 i
of the FSAR for completecess based on information requirements set forth in the " Standard Format" and Content of Safety Analysis Reports for Nuclear Powerplants"(R.G.1.70, Revision 2.)
We recomend that the Catawba FSAR application be accepted. However, all the information needs described in the enclosed report abould be responded to prior to docketing.
I i
R. M. Satterfield, Chief Instrumentation and Control Systems Branch Division of Systems Safety
Enclosure:
AssStated cc:
R. Mattson R. Satterfield 54i1 J99 j
R. Boyd M. Srinivasan s
S. Hanauer T. Dunning W. Pike R. Stevens Q%QOS 7 H. Silver contec :lCSfhDSS.. f b '"(_ T, Da n i g_.
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NRCFORM 313 (9-76) NRCM O240 h ui s. aoVERNMENT PRIMMNO OF FICEs 1978 = S2M14
ACCEPTANCE FEVIEk PEPORT FCh CATA"EA EUCIEAP STATICN 1.
SPECIFIC SECTIONS F EVI EE ED The following secticns of the FSAR were reviewed for completeness on the basis of the " Standard Fornat and Content of Safety Analysis Peports for Nuclear Eover Plants", Pevision 2,
dated Septenher 1975:
- 1. 3 3.11 7.4
- 1. 7 7.1
- 7. 5 1.8 7.2 7.6 3.10 7.3 7.7 2.
ASSESSMENT OF COMPLETENESS CF AREAS REVIEWED The areas reviewed are estinated to be 75% conplcte.
3.
IDENTIFICATICN OF DEFICIENCIES The f ollowing deficiencies sere noted d uring the review of the CNS FSAR. The numbers in the left margin are the ICCS Eranch and Section number [031) followed by the question number and the FS AR Section in paren+hesis. If the question contains a Regulatory Staf f Position, "RSP" is appended to the guestion nunber.
031.001 The FSAR contains conflicting or con f u sin g
( 1. 7) statements which nust be resolved irarder (7) for the review
'o proceed. For eac of the questions below, provide a FSAR revision which is responsive to the staf f 's need for information satisfying the requirements o f the "St andard Format and Content of Safety Analysis Reports for Nuclear Power Plants".
(1) Cla rify t) e discrepancy between the listing of electrical instrumenta tion and control dra wings in FS AP Table 1.7-1 and the ind e x for the Catawba Electrical Schematic books.
(2) Justify the onmission of some of the drawings listed in FSAF 7able
- 1. 7-1 fron your submission.
(3) Provide a cross-reference between Westinghouse drawing numbers (XXXEXIX) which are used in the FSAR diagrans and included in the list of references on these diagrams and the C NS figures.
031. 0 0 2 (RS P) It is the staf f's position that the information
( 1. 3) presented in FS AR Section 1.3 does not satisfy the staff's need to understan d the similarity of Catawba to other plants. Therefore, please
, a p" provide:
541 1'
(1) A detailed cross ref erence to the specific subsections of the EcGuire and/or Watts Bar FSAF that presents the design of systems which are sinilar to Cata wba, and t gusesco#_
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031.002 (2) Idcntify cach difference tetscen the Catawba design and the cited similar designs which have been previously reviewed and approved' by the staff.
0 31. 0 03 (F SP) Table 1.8-1 lists various Regulatory Guides (1. 8) that are not adopted, are par tially complied with, etc. It is the staff's position that all exceptions to full compliance with the Regulatcry Guides Fust be identified and the basis for finding that a specified alternate design approach provides equal or greater protection must be doc umen te d. Therefore, plcase revise the F S AR to satisf y t he st af f's position.
031.004 FSAF Section 3.10.1 references FS AR Table 3. 2.3-1 for (3.10.1) a list of Seisnic Category I systens. This reference (T3. 2. 3-1) is not acceptable in lieu of a list of Cate'ory I instrumentaticn and electrical equipnent as i part of FSAP Section 3.10. Amend FSAP Section 3.1 ) to provide a list of each instrument and each it'em of electrical equipment that is seismica ly qualified.
031.005 The CNS must ncet the conditions of General Design (3.11. 3 )
Criteria 1,
2, 4 and 23 of Appendix A and Sections III and XI of Appendix B (to 10 CFE Part 50) and the national standards identified in Part II
" Acceptance C riteria," of Standard Feview Plan Section 3.11 (which includes IEEE Std 3 23). To ensure that these conditions are met, we regt. ire that the following actailed information about all Class 1E equipment be provided.
(1) Identify all Class 1E equipnent and provide the following information :
(a) Type (functional designation)
(b) Manufacturer (c) Manuf acturer's type number and nodel number (d) The equir 7rt description should include the followint ar applica ble :
(I) Logi equipment (II) Sensors (P ress ur e, differential pressure, temperature)
(III) Control Boards (IV) Instrument racks and panels (V) Connectors (VI) Electrical penetrations
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(VII) Splicis (V III) Terminal blocks (2) Categorize the equipment identified in (1) above into one of the following groups:
031.005 (a) Eguiprent that will expericnce the environrental conditicns of design basis accidcnts and will be required to mitigate said accidents, and t hat will be qualified to f unction in the accident envircnment for the tire required for accident mitigation with saf et y margin t o failure.
(b) Equipaent that will expericnce environmental conditions of design basis accidents, but vill not le requiced to nitigate said accidents, but tFrough which it must not fail in a nanner det riment al to plant safety or accident ritigation, and that will be qualified to withstand any accident cnvironment for the time during which it nust not fail with safety margin to failure.
(c) Iguipment that will e xperiencc environmental conditions of design basis accidents but will not te required to mitigate said accidents, whose f ail ure (in any rode) is considered to not be detrincn'tal to plant safety or accident mitigation, and that will need not te qualified for any accident environment, but will be qualified for its non-accident service environment.
(d) Equipnent that will not experience environmental conditicas of design basis accidents but will be qualified to demonstrate operability under its normal or abnormal service e n vi ronmen t. This equipacnt would normally be located outside of the reactor containment.
(3) For each type of equipment in the categories listed in (2) above provide separatc design specification rcquirement s, including:
(a) The systen safety req uirements.
(b) An environacntal envelopc as a function of time that includes all cxtreme parameters, both marinum and minimum valucs, expccted to occur during plant shutdown, normal oper ation, ab ornal operation, and any design basis event (including LOCA and MSLP), and post e ven t conditions.
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(c) Time requirrd to fulfill its safety function when subject ed to any of the c xtrcrcs cf the envircnment al cnvelope specified in 3 (b) above.
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031.005 (d) Technical basea that justifies the placement of each typc of equipncnt in categorics 2 (b) and 2 (c) listed above.
(4) Provide the qualification test plan, test sctup, test procedures, and acccptance critcria for at least one of each group of equ ipren t in 1 (d) as appropriate to the category identified in (2) above. If any method other than type testing was used for qualification (operat ing experience, analysis, combined qualification, or ongoing qualification), describe that rethod in suf ficient detail to permit an evaluation of its adeguacy.
(5) For each category of equi prent i derai fie d in (2) abcVe, state the actual qualification envelope sinulated during testing (d e fining i se duration of the hostile environrent and the margin in excess of thc design reguirements). If any method other an type testing was used for qualifica 1,
identify the nethod and definc the ectivalent " qualification envelope" so derived.
(6) Provide a surrary of test results that demonst ra tcs t he adequacy of the qualification program.
(7) Identify the qualification docunents which contain detailed supporting inf ormation, including test data, for items (4), (5) and (6) atove.
In addition, to acet the requircrents of Appendix B of 10 CFF 50, the staff requires a statement verifying, (1) that all Class 1E equipment has tsen qualified to the program described abo ve, and (2) that the detailed cualificatica infctration and test results arc available for NEC audit.
031. 0 06 (ES P) It is the staff's position that the requirements (3.10) for seismic and environmental qualificat ion are (3.11) not limited to the equipment which is supplied by Westinghouse. Therefore, please amend the FSAR to acscrito the qualification of all Class 1E
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equipment.
031.007 Section 7.1.1 does not list all safety related systems
( 7.1.1) t hat are provided in the C! S design. Previde a table and appropriate information listing each individual safety related syster and each saf ety related support systcr. Indicate en this table the systers which are designcd an d tuilt by others. She. a conplete conparison
031.007 hetwcon the systers in this plant and those in sirilar plants.
(Sce Cuestion 031.002.)
03i.008 The der 194. kares for syster.s required for safe (7. 4 )
shutdown and for all ot her instrurent ation (7.6) systems required for safety a re incomplete.
Regulatory Guide
- 1. 70 Sect ions 7. 4.1 and 7.6.1 rcquire that the design basis inforaation identified in Section 3 of IEEE Std 279-1971 be provided. Thercfore, revisc the FSAR to satisfy the requirenents of Rcqulatory Guide 1.70, Se cti on s 7. 4.1 and 7. 6.1. Idcntify and justify all exceptions.
031.009 As part of your discussion of conformance with (7.1. 2. 4)
Re gulat ory Guide 1.47, please provide a list of each subsystem which is displayed.
031.010 Section 7.1. 2. 4 " Confot.'an ce to E gulatory (7.1. 2. 4 )
Guide 1.53 and IEEE Standard 379-1972" a d d re s se s only Westinghouse equipment and associated tcpical reports. Provide the cguivalent information for the Balancc-of-Plant portions of the plant safety systene and the auxiliary systems required for suppert of the safety systems.
031.011 Section 7.1.2 of the FSAi doe s not list all of the safety (7.1. 2) criteria that should he opplied to the design and inplcrentation of the i strumcntation and contral systems. Table 7-1 of t ? Standard Feview Plan as augmentcd by the criter a presented herewith presents the current codes, stanoards, and guides with 9hich the sta f f requires conpliance. These additional criteria are: (1) IEEE Std 344-1975- (2) Regulatory Guides 1.78, 1.79, 1.95, 1.10 0, and 1.1 1 ',. In accorda nce with the inplement aticn dater and as they apply to the CNS application, describe che extent to which the r c co n n endat ions and requirenents are met.
Also, the conpliance with Reg ulatory Guides that were addressed in Section 7.1.2.4 is insufficient. Please provide more d(tailed informa tion on how the Catawba design mect-the recommendations of these Regulatory Guides. Identify and justify all exceptions and, where an exception is taken to a Regulatory Guide, demonstrate that the proposed alternative prcsent s an equal degree of conservatisn as the staff position.
031.012 The staff requircs that, for the reactor trip system and (7. 2. 2.1) the engineered sa fety features actuation system, the (7. 3. 2 )
hases, assumptions and results of the FME A be available in the FFAF. Corrcct FSAR Sections 7 2. 2.1 and 7.p. )to
)hk reflect this requirerent.
J' 031.013 orovide the results of an ana lysis which shows that no (7. 3.1) adverso effects will orcur, or a di.ecussion of such adverse effects that could occur, as a result of power interruption to the Encineered Saf ety Features
031.013 Actuation Syrter at any tine following the onset of a LOCA ot other accident condition in the CNS.
Also, provide the bases and a ssumptions upon which the analyses were perforred.
031.014 The discussion of the consequences of instrument air (7. 3. 2. 3) f ailurc s in FSAR Section 7.3. 2.3 is inadequate. Therefore:
(1) Ecfine thc prcferred operating position f or each pneumatically operated valve and control, (2) Identif y all pneumatically coerated valves and controls which are required for or are related to safety, and (3) Identify and iustify all pncumatically operated valves and cs.trols which do not move to the safety f unction position upon loss of air.
031.015 The FSAP does not address the requirements of (7. 2)
Section 7.3.1.3 of the standa rd format (7. 3)
(?cgulatory Guide 1.70). Please provide the inforra tion required for final system' drawings as described in Section 7.3.1.3 of the standard format.
031.016 The design bases f or the reactor trip system (7. 2.1. 2) and engineered safety features actuation system
( 7. 3.1. 2) do not address Section 3 (7) of IEEE Std 279-1971 as required by Regulatory Guide 1.70, Sections 7.2.1.2 and 7.3.1.2.
Please p rovide this design besis information.
031.017 Describ e the design provisions, test equipment, and (7.1) test procedures f cr conductin g rcsponse time tests.
(7. 2)
Also, identify and justify all safety related sensors, (7. 3) signal processing, indicators, actuation devices, and and actuated equiprent which are not response time tested.
031. 018 ( R S P) The list of applicable General Design Criteria (CDC)
(7. 3. 2. 2 )
in FS AP Chapter 7. 3. 2.2 is inconplete. It is the staff's position that the GIC listed in Standard Review Plan Ta hle 7-1 (sce Question 031.011) rust be complie d with. The refore, ple ase revise the PS AR to provide references to the specific FSAR Sections that describe how the GDC reg uirenents are satisfica. Identify and jastify all exceptions.
031.019 (RSP) Your descriptions of compliance to all of the (7. 2) requirer.ent s of IEEE Std 279-1971, Section 4, (7. 3) for the safety related syster-presented in FSAR (7. 4 )
Sectio.ts 7.2, 7.3, 7.4, and 7.6 arc incompletc.
(7.6)
It is t he staff's position th at all safcty
}fl jgg rela ted syrters rus' satisfy the requirements of IIII St d 279-1971 and that CoFpliance be docurented as req uired by Feg ulatcry Guide 1.70.
03).019 Therefore, please revise the FSAF to meet the staf f's requirerents as described in the standard format. Id(ntif y and justify all excepticas.
031.020 For all actions which are to le periorred in a shutdown (7.4) frcm outside of the control reor:
(1) Provide the drawings which show the location and identificatior of the control boards and equipment located thereon, and equipnent and locations within the control roon that support the description of how General design Criterion 19 is inplenented in the CNS.
(2) Confirm that proper procedural guidance for modification cf controls and inetrunentation that may be modified as actual abnornal conditions dictate will be prepared in advance, upgraded as necessary, and available when required.
031.021 list and describe the equipment and s,ystems which (7. 4 )
will te available for cold sh utdown in accordance with the requirements of Section 7.4 of Pegulatory Guide 1.70.
031.022 Frevide a descripticn of how the safety related (7. 5) display instrumentation in the CNS satisfies Eranch Technical Position 23 which is p re sen te d in Appendir 7A to the Standarc Beview Plan.
031.023 Ana?; sis of the systems required for safe shutdown (7. 4 )
and all other systens required for safety (7. 6 )
(FS AR Sections 7. 4 and 7.6 respectively) do not satisfy the requirenents of the standard format, Sect ion s 7. 4. 2 and 7.6. 2.
(General Design Criteria, Begulatory Guides, etc. [see cuestion 031. 011 ] are not d is cu sse d. ) Revise the PS AR to satisfy the regu?.rements of Pegulatory Guide 1.70, Sections
- 7. 4. 2 a nd 7. 6. 2.
Identify and justify all exceptions.
4.
CONCLUSION AND EECOMMENEATIONS We recormend that the CNS FSAR be accepted f or docketing when the questions presented above are responded to in an acccptable manner.
5.
IDENTIFICATICN GP SIGNIFICAFT FEVIEW AREAS A.
Seismic and Environmental Cualification of Cla.s 1E equipment.
qg E.
Thc de sign tases f or the safety rela ted systers.
V9[
h C.
Deviaticns fron the infornation required by the standard format and the Standard review Plan.
Conf iancc with Fegulatory Guide 1.97.
l D.
F.. Use of non-safety equipment in transient ritigation.