ML19209B542
| ML19209B542 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/07/1979 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19209B540 | List: |
| References | |
| NUDOCS 7910100084 | |
| Download: ML19209B542 (25) | |
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OISTRIBUTION:
Docket File EHylten LShao CELO NRC POR-LEngle RVollmer ACM OR3!4 Rdg JStolz TJCarter Reg. Files Memo File SVarga WRussell Puelic info Orcc September 7,1979 NRR Rdg ORoss RIngram R0enise SWcokey LWR Rdg File JXnight GVissing EGCase VMoore
'RReid HR0enton LShao WGamill 055 Occket No. 50-368 EGrimes 0Vassallo I&E (3)
ORMiller, CCR CEisenhut MFA MEMORANCUM FOR: Darrell G. Eisenhut, Acting Director, Division of Operating Reactors, Office of Nuclear Reactor Regulation FRCM:
Ocmenic 3. Vassallo, Acting Director, Division of Project Management, Office of Nuclear Reactor Regulation
SUBJECT:
TRANSFER OF ARXANSAS NUCLEAR ONE, UNIT 2 TO OPERATING REACTORS BRANCH NO. 4 Effective on the date of this memorandum, the safety project management responsibility for Arkansas Nuclear One, Unit 2 is transferred fr m LWR 3 ranch No.1, Division of Project Management, to Operating Reactors Branch No. 4, Division of Operating Reactors.
The licensee, Arkansas Pcwer & Light Ccmpany, received a facility operating license (NPF-6) on July 18, 1978. NPF-6 authori:ed the licensee to load fuel and maintain the plant in Mode 5 (cold shutdcwn condition).
Anencment No. I to NPF-6, issued on September 1,1978, authorized fuil pcwer operation at 2815 MWt. However, the facility sai. temporarily restricted from ocerating at full power until certain tests and other items noted in the license conditions were c:mpleted to the written satisfaction of IE and NRR.
Amendment No. 2 to NPF-6, issued on September 22, 1978, tem:crarib suspended Tecnnical Specification 3.4.1 which alldws enTy cne hour cceration without reactor core ficw in Mcces 3, 4 and 5.
The temcorary cus:ensien was granted for cne.'6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period valid through Cctober 9,1973, :c allow recairs to be c:mpleted on a decay heat suction valve prior :o initial criticality.
Amencment No. 3 to NPF-6, issued on O'ctober 4,1978, revised Technical Scecificaricn 4 5.4.3.5 to :pecify that tne ficw rate for eacn of the con:ainment recirculation fans be ar. least equal a 4500 cubic feet per minute.
Amencment No. 4 to NPF-6, issued on Demoer 17, 1975, corrected a typograpnical error in the Appendix 3 Tecnnical Scecifications.
Amendment No. 5 to NPF-6, issued On November 13, 1978, mcdified the Technical 5:ecifications dealing with One plant Organiza:icnal structure.
(The corres:cnding mccifica:icns were also mace to the Uni-1 Tecnnisal S:ecifica:icns).
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Darrell G. Eisenhut Amendment Nc. 6 to NPF-6, issued on November 18, 1978, provided one-time relief frem Technicsl Spectfication 3.8.1.1.b to allow non-nuclear heatup operation within only one diesel generator and two offsite power systems available before repairs were ccmpleted on the second diesel-generator which experienced mechanical failure on November 9, 1978. The relief was granted fot no longer than three weeks frcm the date of issuance of kendment No. 6.
Amendment No. 7 to NPF-6, issued on December 1,1978, modified or removed three conditions to NPF-6 that had restricted the facility frem going critical and operating at full. power. Amendment No. 7 also modified or removed other license conditions involving acceptable ccepletion of certain conduit penetration fire barrier testing; correction of an implementation date for an action require.d by the fire protection program; completion of acceptable changes needed for protec-tion frca degraded offsite power voltage; and mcdification of the schedule for the remaining actions needed to complete the review of three core protection calculator system positions.
Amenc=ent No. 8 to NPF-6, issued on February 23, 1979, in corporated the " Arkansas Nuclear One Industrial Security Plan, January 11, 1979" into NPF-6.
(This document was also incorporated into the Unit I cperating license).
Amendment No. 9 to NPF-6, issued on March 19, 1979, changed Technical Specificaticn 3.6.1.4 by reducing the minimum initial centainment tempe/ature and pressure to 50 degrees Fahrenheit and a negative 3.0 pounds per square inch gauge, respectively.
Also, the steam generator low water levai trip setpoir.t specified in Tachnical Specification Tables 2.2-1 and 3.3-4 was changed to a value of greater than or equal to 46.6 percent.
Amendment No.10 to NPF-6, issued on March 30, 1979, temporarily suspended Technical Specification 3.6.1.6 which requires that the purge suoply and exhaust system isol-ation valves be closed in Modes 1, 2, 3 and 4.
The temporary suspension was granted for one 30-hour period to allow two eight-hcur purging operations in Modes 3 and 4 only.
Amendment No.11 to NPF-6, issued on May 3,1979, modified the Appencices A and 3 Technical Specifications dealing with the licensee's management organization structure.
(The correspcnding modifications were also made to the Unit 1 Apcendices A and 3 Technical Specifications.)
Amencment No.12 to NPF-6, issued on June 12, 1979, modified a condition to NPF-6 by removing -he restrictions en making any software changes on the core protaction calculator system based on our approval of the licensee's enange recedures. Also,
- ne Technical Specifications were changed to includa a Nuclear Software Ex::ert as a mester of the licensee's Plant Safety Ccamittee. Amendment No.12 also removed another condition regarding implementation of reduncant valve positicn indication in the control rocm which had been verified to be c:mpleted in accordance with previcusly approved design modifications.
The current status of items requiring further staff acticn and the c, ganizations reconsible for ccmoleting Onesa itams are identified in Enclosure 1.
..ists of generic problems and regulatory guides used during the licensing review with references to tne lccations where relevant info: nation or evaluations ci record may be found, are included in Enclosure 2.
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Darrell G. Eisenhut. is a OSE memorandun which su:marizes the environmental status of the project and transfers the environmental project management responsibility from OSE to 00R. Enclosure 4 is the service list for the plant. Enclosure 5 is the licensee's list for direct. distribution of amendrients, etc. Enclosure 6 is a list of documents that are relevant to plant operations subseouent to the issuance of NPF-6.
Sy copy of this memo, 055, IE, ~MPA, ELD, ADM. Regulatory Files, Public Infor ::ation and Public Proceedings are being notified of the folicwing' safety personnel changes which are to be effective on the date of this memorandum. Enclosure 3 lists the
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From Project Manager L. Engle G. Vissing
- Sranch Chief J. Stolz R. Reid Assistant Of rector S. Yarga W. Gamill Licensing Assistant E. Hylton R. Ingram p' W Ocmenic B. Yassallo, Acting Director Division of Project Management
' Office of Nuclear Reactor Regulation
Enclosures:
1.
Current Status of Items Requiring Staff Action 2.
C'.rren Status of Generic Review Items 3.
OSE Transfer Memorandum 4
Facility Service List p.A 0/ Pdf0 S.
Licensee's Distribucion Lis, i
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CURRENT STATUS OF ITEMS RE00 RING STAFF ACTION ARKANSAS NUCLEAR CNE, UNIT 2 COCKET NO. 50-363 FACILITY OPERATING LICEN'SE NPF-6 The current status of the items requiring further staff action and the organizations responsible for comoleting these items are as folicws:
1.
Fuel Performance License Condition 2.C(3)(~ ) stipulates that th'e licensee sholl., prior to a
startuo for the cycle of operation in which burnups greater than 20,000 meg = watt days per ton of uranium are expected to be obtained, provide for Ccmmission review and obtain Ccmmission approval of revised fission gas release calculations and other affected analyses utili:ing fission gas release calculational methodology approved for burnups greater than 20,000 megawatt days per ton of uranium. This matter is discussed further in Secticn 4.2.1 of Supplement No. 2 to the Safety Evaluation Report (SER).
Tha Core Performance Branch (DSS) will review any topical recort submitted and will prepare the input to a SER. The assigned plant specific review for this mattar will be performed by the Reactor Safety Branch (COR).
Management responsibiltty for this matter will be carried out by Operating Reactors Branch No. 4 (00R).
2.
Instrument Trio Setsoints Grift Allowance License Condition 2.C(3)(d) stipulates that the licensee shall submit for Ccmmission review certain information for eacn reactor protection system and engineered safety feature instrumentation channel for incorporation in the Technical Specifications (TS). A document was subnittec by the licensee on Fecruary 23, 1979.
e The Plant Systams Branch (COR) will maintain primary review resconsibility for tnis matter. A SER for nis review will be c:moleted by J. Sur:cin (?S3) criar to Novemoer 15, 1979. Managament respcasibility for this matter wili :e carried out by Cperating Reactort 3 ranch No. 4 (CCR).
- 3. _, Fire Protection License Condition 2.C(3)(e), as modified by Amencment No. 7 to NPF-6 stipulates that the licensee shall c0cclete certain modifications by the indicated d;tes in accorcance with our findings as set forth in NUREG-0223, " Fire Protect.cn SER.*
This matter is discussed furtner in Section 9.7 of the SER and Sucplement Nn. 2 nereto.
Table 3.1 of NUREG-0223 is a summary of :ne cutstanding items.
NUREG-0223 recuires tne if censee to succit recuests for TS changes on items 3.5, 3.11, 3.14 anc 3.15 anc accit cnal information On items 3.5 and 3.7 at least 90 4
days criar to.9cdification. Adciticnal information will te recuested from ne licensee by CR3*a on items 3.1, 3.3, 3.9 and 3.18 to allcw ccmoletien Of the -eview arecess.
The slant Systems 3ranca ( CR) will maintain 1, i s~ s, 7?-)
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. primary review responsibility and will prepare the input to a SER within 30 days of receipt of the information on the aforementioned items.
On January 15, 1979, the ifcensee provided information to support the deletion of Item 3.10 from Table 3.1 of NURE 40223. The Plant Systems Branch (COR) is reviewing the status of this matter.
A letter from the Itcensee dated July 17, 1979 provides the latest status of completion of items Ifsted in Table 3.1 of NUREG-0223. The Office of Inspection and Enforcement will verify that the modifications have been satisfactorily implemented. Management responsibility for this matter will be carried out by Operating Reactors Branch No. 4 (00R).
3.(a) Fire Protection - NUREG-0223, Table 3.1 Item 3.12 Fire Damoets On March 23-24, 1979 by telephone, and on May 1, 1979 by Licensee Event Report, it was identified that 32 fire dampers wera not instal'ed ac required by architactural design specifications. Nine of these dampers were for safety related area protection. A continuous fire watch was established for all affected safety related areas as required by TS 3.7.11.
The licensee submitted a recuest on April 17, sucolemented on May 18, 1979, for a modification to TS 3.7.11 to exempt four l' cations frca the requirements of the TS until o
Septemoer i,1979 wnen the damper installation is. expected to be ccmoleted.
The Plant Systems Branch (COR) reviewed this request and submitted input to the SER. An amendment will be issued by Operating Peactors Branch No. 4 (00R) after receipt of the required input and concurrence from De Standard TS Group (00R). The licensee has advised us verbally that the mendment request may be withdrawn since the damper installations will t,e completed shortly.
The Office ci Inspection and Enforcement will verify that the modifications have been satisfactorily imolemented. Management responsibility for this matter will be carried out by Operating Reactors Branch No. 4 (00R).
4.
Overoressure Miticatino Svstem License Conditon 2.C(3)(f) stipulates *.nat the licensee snali, prior to star:uo folicwing the first regularly scheduled refueling outage, acnieve full imolemettation of its proposed overpressure mitigating system described in the licar.see's letter dated October 11, 1977.
The licensee will submit a descriot'on of One interlock or alarm to be installed on the isciation valves wnich will be reviewed by ICSB and RSB (CSS) to assure coroliance wi:h applicable standards and criteria. RSS will provide :he input to an SER within 60 days of receipt of the information frcm the licensee.
The licensee will submit a request for a TS involving surveillance requirements for the relief valves. The Plant Systems 3 ranch (CCR) will be resconsible for the review.
his matter is discussed further in Secticn 5.7 of Sucolement No. I to the SER.
The Office of Inspec-icn and Enforcement will verify :na: :ne sys:em has teen satisfactorfly imoiementec. 'darngement.resconsibility for Onis matter will be carried ou: by 0;erating Reac: ors ~3rancn No. 4 (COR).
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Verification of Transient Analysis Code License Condition 2.C(3)(g) stipulates that the licensee shall complete tests to verify the use of the CESEC Code during the initial s ascension testing program and submit the results for Comm,tartup and power ission review and approval. This matter is discussed further fri Section 15.4.2 of the SER and Supplement No. 2 thereto. The Office of Inspection and Enforcement indicated on December 14, 1978, that instrumentation was in place for the CESEC code verification.
The Analysis Branch (OSS) will maintain primary review responsibility for this matter and will prepare the input to a SER within 90 days after receipt of the report. Management responsibility for this matter will be carried out by Operating Reactors Branch No. 4 (CCR).
6.
Main Feedwater System Modifications License Condition 2.C(3)(h) stipulates that the ifcensee shall, prior c :::rtup following the first regularly scheduled refueling cutage, achieve full imple-mentation of its proposed modifications to the main feedwater system to preclude unacceptable mass and energy blowdown into the containment in the event of a main steamline break accident. This matter is discussed further in Section 5.2.1 of Sucolement No. 2 to the SER, and in an interoffice memo da:ed June 6,1979 from R. Boyd to H. Thornburg.
A TS surveillance requirement for the redundant main feedwater isolation valve..ay benecessary. The Plant Systems 3 ranch (COR) will review this matter and prepare the input to a.. SER including the evaluation of the changes tc TS.
The Office of Ins:ec:fon and Enforcement will verify that the modifications have been satisfactorily implemented. Management responsibility for this matter will be carried out by Operating Reactors Branch No. 4 (00R).
7.
Containment Radiation Monitor License Condition 2.C(3)(1), as modified by Amendment No. 7 to NPF-6, sti:ula:es
- nat the licensee snall, prior to July 31, 1980, submit for Comission review and approvai, documentation wnich establisnes :ne adequacy of the cualif6ar'ans of the containment raciation monitors located inside the containment and snall complete the installation and testing of these instruments to demonstrate that they mee: the operaoflity requirements of TS 3.3.3.5.
he Instrumenta:f on and Control Systems Branch (CSS) will maintain primar."
review res:cnsibility for this ratter and will prepare :he input to a SER including the evaluation of the changes to 75. Vanagecen: resconsibility for :nis matter will be carried out by Coerating Reactors 3ranca No. a 'CCR).
3.
Core Pe tec-icn Calcula or Svstem (CFCSI ho: arts (1), (2) and (3) of License Condition 2.C(3)(k), as modified by Amendments Nos. 7 and 12 :o MPF-6, stipulate that the startup re:or: required by TS 6.3.1
- e supplemented to include.ne results of testing associatec witn CPCS Position Nos. 1, 5 and 12, res:ectively. An interoffice memo from S. Hanauer (DSS) :n 1 ] s" ~,'
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P0011Ol18M Acril 6,' l979 describes the Ccemission's responsibilities relating to s ptember 13-14, 1979 by memters of 055.
CPCS. A site visit is scheduled for e
(1) CPCS Position No.1, Power Distribution ~ Alcorithm Subpart (1) of License Condition 2.C(3)(k), as mcdified by Amendment No. 7 to NPF-6, stipulates that the startup report required by TS 6.9.1 be supplemented to include the results of the startup verification testing wnich demonstrates the conservatism of the calculation of the pcwer distri-bution uncertainty factors. This matter is discussed further in Section 0.3.5 of the SER and Supplement Nos. I and 2 thereto.
The Core Performance Branch (OSS) will maintain primary review respon-sibility for this matter, and will prepare the input to a SER within 90 days of receipt of the testing report.
The assigned reviewer for this matter in the Core Perfor ance Branch (055) is R. Schemel.
In addition, the Plant Systems and Reactor Safety Branches (DCR) will monitor this matter in order to beccme knowledgeable about the CPCS.
D. Tondi and J. Seard will monitor this matter for the Plant Systems Branch and S. Weiss will monitor for the Reactor Cafety Branch. Management responsibility for this matter will be carried out by Operating Reactors 3 ranch No. 4 (DCR).
(2) CPCS Position No. 5, Cable Secaration Subpart (2) of License Condition 2.C(3)(k), as modified by Amendment No. 7 to NPF-6, stipulates that the startup report required by TS 6.?.1 be supplemented to include the results of measurements frcm the startup testing program which demonstrate that noise or electremagnetic inter-ference effects from non-Class IE circuits which are in close proximity to Class IE circuits are within previcely established acceptable ranges.
This matter is discussed further in Section 0.4.1.2 of the SER and Supplement Nos. I and 2 thereto.
The Instrumentation and Control System 3 ranch (055) will maintain primary review responsibility for this matter, and will precare the incut Oc a SER within 90 days of receipt of the testing re:: ort. The assigned reviewer for this matter in the Instrumentation and Control Systems Branch is J. Joyce.
In addition, the Plant Systems 3 ranch (CCR) will monitor this matter in order to bec me kncwledgeable about the CPCS.
D. Tondi and J. Beard will monitor this matter for the Plant Systems Branch. "anagement res:cnsibility for this atter will be carried out by Operating Reactors Brancn No. 4 (DCR).
(3) CPCS Position No. 12. Electrical Noise and Isolation Suc;:ar (3) of License Conditicn 2.C(3)(k), as mccifiec by Amencment No. 7 to NPF-6, stipulates tnat the startuo re: ort required by TS 5.9.1 be sucolemented to include the results of measurements from the star ua :esting program whien demonstra:e that noise or electr: magnetic interference effects ucon the acera: ion of the co:ical isolators are wi:nin previously establisned accactacle ranges. This matter is discussed furtner in Sec:icns 0.1.1.1 and 0.1.2.1 :# Su:clemen Nos.1 and 2 to the SER.
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P00ROR8NAL The Analysis Branch (055) will maintain primary review responsibility for this matter, and will prepare the input to a SEK within 90 days of receipt of the testing report.
The assigned reviewer for this matter in the Analys.is Branch is L. phillips.
In addition, the Plant Systems Branch (00R) will monitor this matter in order to beccme knowledgeable about the CPCS.
D. To.di and J. Beard will monitor this matt'r for the Plant Systems Branch. Management responsibility will be carried out by Operating Reactors Branch No. 4 (COR).
9.
CEA Guide Tube Survefilance procram License Condition 2.C(3)(1). stipulates that the licensee sh'aff, prior to startup folicwing the first regularly scheduled refueling autage, submit for Comission review and approval the results of a surveillance program conducted on the design modifications to the control element assembly (CEA) guide tubes.
This matter is discussed further in Sect' a 4.2.4 of Supplement No. 2 to the SER. The licensee will provide the surs.11ance progran for review at least 90 days prior to shutdcwn for the first refueling.
The Reactor Safety Granch (COR) will maintain primary review responsibility for enis matter, and will approve the program and prepare the input to ' SER a
on the results of the surveillance program. Management responsibility for this matter will be carried cut by Operating Reactors Branch Nc. 4 (00R).
10.
IE Bulletin No. 79-06 On April 14, 1979, IE Bulletin No.79-06B was transmitted to the licensee.
IE Sulletin No.79-068 specified certain acticns to be taken by the licensee to prevent the occurrence of an event similar to that which cccur-red at Three Mile Island Nuclear Station, Unit 2 on March 28, 1979.
By letter dated April 24, 1979, the licensee provided its response to IE Bulletin 7-068. Based en our review to date of the information provided by the l'idriee, we have concluded that, wnile we have identified certain areas in nich additional action or infor ation is needed, the licensee has correctly interpreted IE Sulletin No. 79-C63. The licensee has stated that no changes to the TS are required at this time in response to tne actions required by IE Sulletin 79-068.
A request for additional informatien was issued on July 25, 1979, with re-spense requested by August 10, 1979. The assigned project manager is I. Vilialva.
On July 26, 1979, IE Sulletin No. 79-C6C was transmitted to the licensee.
IE Bulletin No.79-06C specified 1cng and short term acticns to be :aken in ceder to alleviate the concern over delayed tripping of -he RCps aftar a LCCA.
The rescense to Su11etin 79-C6C is not yet available, :ut will te :c-ordinated my I. Vilialva.
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Further staff actions required as a result of IE Sulletin 79-06 will be carried out as a joint effort between the Sulletins and Orders Task Force and COR. Bulletins and Orders Task Force will have primary management responsibility for this item.
- 11. TMI-2 Generic Review of Coeratine CE Plants' As a result of the accident at.TMI-2, the licensees of plants utilizing Combustion Engineering nuclear steam supply systems han for :ed an owner's group to address certain TMI-2 related matters such as our request for additional information concerning small break loss-of-ccclant accident analyses. Our stipulation for this study is documented in our letter to the licensee dated June 6,1979. The licensee has advised us that its re-sponse to these matters will be provided to us by late July 1979 in order for us to ccmplete our generic evaluation for Comcustion Engineering plants.
Further staff actions required is a result of this matter have bee'1 assigned to the Bulletins and Orders Task Force. COR will interface with t:.e Bulletins and Orders Task Force as necessary for any plant specific actions that might be required in the future.
12.
EFW Pumo Rescense Time The licensee submitted a. request on July 24, 1979 for a modification to TS Table 3.3-5 relating to emergency feedwater pump response times.
CCR review responsibility will be assigned in accordance with routine procedures. Management responsibility for this matter will be carried out by Operating Reactors Branch No. 4 (ORB #4).
- 13. Asvmmetrie 31cwdcwn loads on Reactor Primary Ccolant Systems - PWR Reactor vessel supports and reacter internals are discussed in the SER pp. 3-17 througn 3-19 in Supplement 2 pp. 3-1 and 3-2, and in a submittal frca the licesee en January 17, 1978.
S. Hosford (ES) is the task coordinator. The Analysis Branen (DSS) is responsible for tne site specific ccmcarison between the CENp0-42 vs. CEP. ASH 48 models.
The task coordinator will inform CRBf4 of the cutstanding items concerning this issue prior to August 21, 1979.
Management responsibility for this matter will be carried out by CRSM.
14 Con ainment Leak Testino - Accendix J Accendix J requiremnts are discussed in :ne SER c. 6-7; Sucplement 2 po. 6-6 and 6-7; and in the 75 pp. 3/4 6-2 through 6-5.
Amendment No. I to the Operating License NPF-6, issued Septemcer 1,1973, authoricec a three year exemotion regarding testing of primary containment air locks.
- 3. Arndt (SCSS) is involved in the deveicpment of a general exerpticn regarding centainment ieak testing wnicn snculd be resol /ed prior o -ae time wnen the licensee's exemption expires.
- CR review ressensibility will be assigned as necessary in accordance with ecutine precedures. Management responsibili y for this matter will be carried cut by CRSpa.
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A generic latter was issued en November 11, 1977, to which the licensee responded on Decemcer 30, 1977. Operating Reactors Branch No. 4 will forward copies of these letters for review to the Power Systems Branch (OSS).
An evaluation of this generic issue will be submitted to ORB #4 within 30 days of the receipt of the information.
Management respon'sibtlity will be carried out by CRS#4 16.
Inservice Testinc - pumos and Valves Inservice testing is addressed in the SER p. 3-16, Supplement 2 pp. 5-!
and 5-2, TS 3/4-02, 3/4-03 and 3 3/4 0-3.
The Mechanical Engineering 3ranen (055) will maintain' primary review responsibility for this matter.
. CSS will be contracting the review of the licensee's testing program, through the Cepartment of Energy, with the Idaho Nationai Engineering Laboratory (INEL).
H. 3rmater (ME3) will inform ORS #4 if changes in the status of the review occur and will update the target date for completion as necessary after the contract with INEL has been finalized. As per Supp1(tent 2 p. 5-2, the acceptability of the licensee's program is to be deterr.dned prior to the start of facility ccatercial operation (approx.
9/20 to 9/25/79). Adequate communication is required between all parties aforerentioned to insure that timely alternatives are available due to the fact that the centractor's review will not be completed prior to the licensee's c:mmercial operation date.
1!. Leakace of Containment Isol.ation Valves w'ith Resilient Sea:s This generic issue (3-20) is based u:en -IE Circular 77-11 is:ued in September 1977. The lead engineer on this generic issue is C. Grimes of the plant Systems 3 ranch (CCR).
Action on this isste is teing held pending resolutien of generic item 3-24 relating to venting and urging cantainments while at full pewer.
Management respcnsibiif ty will be carried out by CRB#1 when the issue is reopened.
18.
pWR 3econcary Water Chemistry Monitorine Recuirements This f ssue is addressed in the SER p. 5-11 and TS ;o. 3/4 7-11 througn 3/4 7-12.
By letter from the Comeission dated August 2,1979, tne licensee was requested o sucmit witnin 60 days a procosed amendment to license NpF-6 that will include the secondary water :hemistry program.
The 3rogram will be referenced in a condition to the Itcense and will replace the existing TS on secondary water chemistry.
Management res:ensibility for the tcdification to tne license will be carried out by CRSva.
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. 19. Puro Succort - Lamellar Tearinc [ Fracture Touchness) (C-6)
A generic letter was issued on December 5,1977, to which the licensee responded on Cecemoer 19, 1978. A MUREG will be issued in Septemoer 1979 on this generic issue. The licensee's scecific review,'will be performed by a contractor. The Engineering Branch (00R) is respcnsible for the supervision of the contract. This generic issue is to be ccepleted by 1982.
Management rescensibfif ty will be carried out by ORB #4
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300R ORBlML CURRENT STATUS CF GENERIC REVIEW ITEMS ARXANSAS NUCLE.aR ONE, UNIT 2 The current status of the generic review items are listed belcw. Except for the regula cry guides, the generic review items correspond to those listed in the ONRR Operating Reactors Licensing Sumarf (CCR Generic Issues).
A.
Items which have been resolved and require no further NRC action:
Item Reference 1.
ECCS Evaluation SER p. 6-10; Suppl. 2 pp. 6-7 through 6-9 (A-8) 2.
Effluent Treatment Systems SER pp.12-1 througn 12-4 (ALARA) (A-2) 3.
Emergency Planning SER pp. 1.?-3 & 13 4; Suppl. 2 p. 13-1 (3-16) 1 Ffiter Tech Specs TS pp. 3/4 7-17 thr:ugn 3/4 7-19 (C-4) 5.
Ficed of Eeuiprnent Important SER pp. 6-10 & 10-2; Suppl. 2 pp. 6-716-10 to Safety (3-11) 6.
Fracture Tcughness Requirements SER pp. 5-2 & 5-3; Suppl. 2 p. 5-1 Appendix G (A-7) 7.
High Energy L*.ne Break SER pp. 3-7 through 3-9 3.
In-Reactor Growth of CE Supol. 2 p. 4-1 Poison Reds (3-15) 9.
Inservice Inspection of ?hR SER ;;;:. 5-11 3 5-12; 75 pp. 3/4 2-6 througn Staam Genera:or Tuoes 3/4 4-12 (3-12)
- 10. Qualifications of Raciation SER ;:o.13-1 3 11-2; TS pp. 6-1 thrcuch 5-5 3rc:e :1cn l4anager (C-3)
- 11. Resoira: cry Protection Program (A-6)
- 12. Steam Genera:cr Feedwater 1cw Instability (3-7) 13.
Potential Equi;: ment Failure SER o. 3-2; Su::pl. 2, pc. 3-1 13-2; NpF-Associated With Cegraded Grid Cenci fon 2.C(3)(0) as Icdified by Voltage (3-23)
Amend. ent No. 7.
11 E '29
REGULATORY GUIDES 14.
Net Position Suction Head for SER pp. 5-4 & 5-9 Emergency Core Cooling and Containment Heat Removal System Punps (R.G.1.1) 15.
Assumptions Used for Evaluating SER p. 2-11 the Potential Radiological Cont quences of a Loss of Coolant Accident for Pressurized Water Reactors (R.GL 1.4) 16.
Independence 3etween Rendundant SER. pp. 8-1 & 8-3 Stancby (Onsite) Power Sources and Between Their Distributien Systems (R.G.1.5) 17.
Control of Combustible Gas SER pc. 5-6, 5-7 & 5-15; Suppl. 2, p.15-6 Cancentra:4ons in Containmen:
Following a Loss of Coolan Accident (R. G.1.7) 18.
Personnel Selection and Training SER pp.12-1 & 13-2 (R. G. 1.3 )
19.
Selection of Diesel Generator Set SER ;p. 8-1 & 3-3 Capacity for Stancby Power -
Supplies (R.G.1.9) 20.
Instrumentation fer Earthquakes SER p. 3-10 (R. G. 1.12 )
21.
Spent Fuel Storage Facility SER pp. 2-6, 9-2, 9-3 & 9-4 Design Sasi s (R. G.1.13 )
22.
Reactor Coolant R;mp Flywheel SER ;p. 5-9 3 5-10 Integrity (R.G.1.14) 23.
Pr::ection of.'bclear Power SER p.13-5; Supol. 2 p.13-1 Plants Agains: Incus: rial Sacotage (R.G.1.17 )
24.
Structural Acce::ance Test for SER p. 3-11 Concrete Pri=ary Reactor Containments (R.G.1.13 )
1IJ>
,,0 3
?00R ORIGEL
- 25. Comprehensive 'libration Assess-SER p. 4-5 ment Program for Reactor Internals During Preoperational and Initial Startup Testing (R. G. 1. 20 )
i
- 26. Measuring, Evaluating, and SER pp.11-5 & 11-6 Reporting Radioactivity in Solid Wastes and Releases of Radicar.tive Materials in Li. quid and Gaseous Effluents frcm Light-Water-Ccoled Nuclear Powe P1 ants (R.G.1.21)
- 27. Cnsite Metacrological Programs SER pp. 2 1 & 2-12 (R. G. 1.23 )
- 28. Assumptiens Used fer Evaluating SER p.15-17 the Potential Radiological Consecuences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (R. G. 1.25 )
- 29. Ultimate Szat Sink for ibclear SER p. 9-5 Power Plant s (R.G.1.27) 30~. Seismic Cesign Classification SER pp. 9-2, 9-10 & 10-2 (R. G. 1. 29 )
- 31. Criteria fcr Safety-Related SER p. 3-1 Electric ber Systems for Nuclear Power 91 ants (R. G. 1. 32 )
- 32. Nonmetallic Tnercal Insulation SER pp. 5-4, 5-7 & 6 - 15 for Austenitic Stainless Steel (R. G. 1. 26 )
- 33. Cuality Assurance Requirements SER p. 5-7 for Cleaning of Fluid Systems and Asscciated Compenents of Wa*e r-Ccolec Nuclear Eower
?l ants (R.G.1.27 )
l ! 3.]
3}
. 24 Preoperational Testing of SER p. 8-1 Recundant Cn-Site Electric Power Systems to Verify Proper Lcad Groua Assignments (R. G. 1.41)
- 35. Control of the L'se of Sensitized SER pp.
4-5~, 4-6, 5-5, 5-6, 5-7 & 5-14 Stainless Steel (R.G.1.44)
- 36. Reactor Coolant Pressure Soundary SER p. 5-9 La'akage Cetection Systans (R. G. 1. 45 )
- 37. Pfotection Against Pipe Whip SER pp. 2-7 & 3-8 Inside Centainment (R.G.1.46)
- 38. By;assed and Ino;erable Status SER p. 7-19 Indication fcr Nuclear Power Pl ant Safety Systems (R.G.1.47)
- 39. Cesign Limits and Loading Ccm-SER pp. 2-15 & 5-1 binations for Seismic Category I Pluid Systen Ccaponents (R.CL 1.?S )
- 40. Centrol cf Preheat Temperature SER pp. E-6 & 5-7 for Welcing of L:w-Alicy Steel (R.G. 1.50 )
- 41. Design Basis Ficeds for tuclear SER p. 2-13 Power Plant s (R.G.1.59)
- 42. Camping Values for Seismic Design SER p. 2-9 of Nuclear Power Plants (R.G. 1.61)
- 43. Installation of Overaressure SER pp. 2-17 & 5-2 Protecticn Cevices (R.G.1.57 )
- . initial Test Programs far Water-SER p.11-1 Cccled Reacter Power Plants (R. G. 1. 63 )
- 45. Assumptiens Lsed fcr Evaluating SER p.15-11 a Control Red Ejection accident for Pressurized Water Reacters
'R. G. 1. 77 )
11i~
' _3. c7 i
. 46. Preoperational Testing of E=er-SER pp. 5-12 & 14-2; Suppl. 2 p 14-1 gency Core Cooling Systems for Pressurized Water Reactors (R. G. 1. 79 )
- 47. Inservice. Inspection of Fressur-SER p. 5-12 ized Water Reactor Steam Generator Tbbes (R.G.1.83)
- 48. Ccde Case Acceptability-AS.ME SER p. ' 3-3 Section III Design.and Fabrication (R.G.1.84)
- 49. Coce Case Acceptability-ASPE SER p. 2-3 Secticn III Materials (R.G.1.85)
- 50. Protection of POclear Fower SER p. 6-14 Plant Centrol Recm Cperators Against an Accidental C11crine Release (R.G.1.95) 51. Methccs for Estimating Atmes-SER pp. 2-11 & 2-12 pheric Transcort and Dispersion of Gaseous Ef fluents in Routine Releases fran Light Water Cccled Reactors (R.GL 1.111) 52.
Fire Protectien Guidelines for SER p. 9-11 Nuclear Power Pl ants (R.G.1.120 )
53.
Information Relevant to Maintain-SER p. 12-1 ing Occupatenal Radiation Exposure as Low as is Reascnably Achievable (Nuclear Power Reactors) (R.G. 8.8) 54 Ccerating Philosegny for Maintain-SER p.12-1 Cccc ational Radiation Expcsures as Lew as is Reasonably Acnievable (R.S. 5.10)
- 3 a
as
. 3
3.
Items which have been evaluated in light of current NRC requirements /
guidance and which are presently unresolved. Further action by NRC and/or the licensee may be required in the future.
1.
ATWS - Lono Term Procram
~
A meeting with Combustion Engineering will be held on August 17, 1979 regarding the submittal of an ATWS generic report. The Division of System Safety is reponsible for the review and expects to present the generic analysis to the Ccomission by the spring of 1980. Site Specific requirements should be available by the summer of 1980.~. A. Thadani (OSS) will prepare the input for resolution of this generic issue. Management responsibility will be carried out by Operating Reactors Branch No. 4.
2.
Fuel Rod Scw Effects (00R Generic Issue 3-13)
This issue is discussed in the SER pp. 4-15 and 4-16 and in Supplement No. I pp. 4-1 and 4-2.
This facility is the first to use Cembustion Engineering's 16 x 16 fuel assemblies. Folicwing the first cycle of operation, reanalyses along with rod bcw measurements submitted by the licensee or fuel vendor will be reviewed by the Reactor Safety Branch.
Management responsibility will be ca ried out by Operating Reactors Branch No. 4.
C.
Items which have been evaluated in light of current NRC requirements / guidance and which are unacceptable.
Item Reference None None D.
Items of which their status needs further review or clarificatien.
The Division of Cperating Reactors will assume primary review responsibility for these itens. Management responsibility will be carried cut by Coerating Reactors Branch No. 4 ls.
3h
Iten 1.
Generic Issues (ONRR Operating Reactors Licensing Surrary)
A-2 Appendix I - ALARA A-9 Pressure Yessel Beltline Material Surveillance A-10 Contingency Planning A-11 Guard Training Plans A-12 Vital Area Analysis 8-3 Moder ator 011ution 3-8 PWR HPSI-LPSI Flow Resistance 3-9 Charging Systems Pipe Vibrations S-17 Technical Specifications Surveillance for Hydraulic Snubbers 3-21 Loss of 125-V CC Sus Voltage With Loss of Annunciatien System B-22 Technical Specification Surveillance Requirements for Mechanical Snubbers 3-24 Venting and Purging Containments Whfie at Full Power and Effect on LOCA B-25 Inadvertant Safety Injection Curing Coaldown 3-36 Resistance Temperature Cetector (RTO) Response - CE 3-37 Steam Generator Tube Centing and Support Plate Modifications - CE 3-39 PWR Pressure-Temperature Limit Technical Specifications 3-41 Fire Protection - Final Technical Specifications (including SER Supplements) t C-7 Fuel Handling Accident Inside Containment C-12 Saron Solubility Ouring Long Term Cooling Following LOCA 0-4 PWR Reactor Vessel Cavity Seal Ring Missile Potantial D-6 Peaking Model Change for CE Reactor Core 0-3 Ceficiency in Chem. Addition to Containment Sorays E-1 Spent Fuel Fool Expansions E-3 Core Reloads Requiring Prior NRC Approval E-6 CEA Position Indication bailures - CE E-7 Reactor Protecticn System Logic - CE Cracking in Feedwa,ter Lines - PWR li::
35
. E.
Items wnich are not applicable to ANO-2.
Item R eference l.
ATkS - Short Term Program (Cat B BWR's) 2.
SWR Safety-Relief Valve Surveillance 3.
ECCS Reevaluation to Account for Increased Vessel Head Fluid Temp 4.
Mark I Containment - Short Term Program Technical Specifications 5.
Mark I C ntainment Evaluation Long Term Pr gram 7
Mark I Safety / Relief Valve Line Restraints in the Torus
- 8. ' Non-Jet Pump (NJP) BWR Core Spray Cooling Ccefficients 9.
Powr Level fer RWM Operability 10.
Pressuri:tr Featuo Rate-Westinghouse P'aR ' s
t sstinghcuse Irrer in Metal-Water Reaction Calculation
- 13. Westingr.cuse Uc;er Plenum ECCS Injection - L:ng Range
]1E7 3r
~'
s J
~)
V
ENCLOSURE 4
' FACILITY SERVICE LIST g
ARKANSAS NUCLEAR ONE, UNIT 2 00CXET NO. 50-368 FACILITY OPERATING l.ICENSE NPF-6 Mr. Willian Cavanaugh III Executive Director of Generation & Construction Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203 cc: Mr. David C. Trimble Honorable Ermil Grant Manager, Licensing Pcpe County Judge,
Arkansas Pcwar & Light Company Pope County Courthouse P. O. Box 551 Russellville, Arkansas 72301 Little Rock, Arkansas 72203 U. S. Environmental Protecticn Phi l i p K. Lyon, Es q.
Agency House, Holmes & Jevell ATTN:
EIS Cocrdinator 1550 Tower Snilding Regien VI Office Little Rock. Arkansas 72201 1201 Elm Street Oallas, Texas 75270 Mr. E. H. ST.ith, Project Engineer Bechtel Pover Corporation Mr. James F. O 'Hanlon San Francisco, California 94119 Ceneral Fanager - Arkansas Nuclear Cne Mr. Fred Sernatinger, Project Manager P. O. Ecx 608 Combustion Engineering, Inc.
Russellville, Arkansas 72E01 1000 Proscect Hill Road Windsor, Ccnnecticut C6095
.t. Charles 3. Erinkman, Manager Washingten itclear Operations C-E Power Systems Combustion Engineering, Inc.
4853-Cordell Avenue, Suite A-1 Sethesda, Maryl and 20014
.t. E. F. Wilson, Director Bureau of Envirencental Health Sorvices a815 West Markham Street Little Reck, Arkansas 72201
]~]'
'3/
ENCLUSURE 5 LICENSEE S DISTRIBUTION LIST, ARXANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-358 FACILITY OPERATING LICENSE NPF-6 Acolication, Generai Information and Safety Analysis Recert and Amendments Mr. E. F. Wilson, Di rector Sureau of Environmental Health Services 4815 West Markham Street Little Rock, Arkansas 72201 Honorable Ermil Grant Pope County Judge Pope County Courthouse Russellville, Arkansas 72801 U. S. Environmental Prc ection Agency ATTN: EIS Cordinator Region' VI Office 1201 Elm Street Dallas, Texas 75270
~
Environmental Recort and Amencments and Sucalemfnts (Nuncers in parentneses incicate numcers of ccples)
Decar: ment of Ccmmerce Decar: ment cf I nterier Cr. Sidney R. Galler (5)*
Mr. Bruce Blanchard, Director (18)
Deputy Assistant Secretary for-Office of Environmentai Projects Env.ironmental Affairs Review, Rcom 5321 U. S. Department of Commerce U. S. Departnant of Interior 14th & Constitution, N. W., Rn. 3425 18th & C Streets, N. W.
Washington,D. C.
20230 Washington, D. C.
20240 Mr. Rcbert Ochinerc, Directer (1) cc :
(Transmittal letter cnly)
Naticnal Cceanegraphic Ca:a Center Chief Envircemental Data Service Division of Ecological Servicer National Oceanic and A:mespheric Sureau of Spor: Fisheries &
Acninistration Wildlife U. S. Department of Cc=merce U. S. Cepartmen: of Interior Washing:en, -
C.
20235 18th & C Streets, N. W.
Washington,C. C.
20240
- Generic - 13 ccpies Amendments - 5 copies 1
.s~
. Decartment of HEW E nvironmental P rotection Agency (C ont' d Pr. Charles Custard, Director (2)
Office of Environmental Affairs Mr. Devereaux Barnes (1)
U. S. ' Oepartment of Health, Education Effluent Guidelines Division and Welfare, Room 4740 U.S. Environmental Protection Age-330 Independence Avenue, S. W.
Waterside Mall, b. 905 E. Tower Washington, D. C.
20201 401 M Street, S. W.
Washington, D. C.
20460 Federal P cwer Commission Ms. Geraldine '.erdig (1)
Chief (1)
Environmental Evaluation Branch Bureau of Power Office of Water Programs Federal Power Comnission, b. 5100 U.S. Environmental Protection Ace 825 North Capitol Street, N. E.
Wa terside Ma l l, Rm. 2818 E. To wer Washington, D. C.
20426 401 M Street, S. W.
Washington, D. C.
20460 Federal Power Conraission, b. 6100 (1).
S25 North Capitol Street, N. E.
Dr. Bern Kahn (1) -
Washington, D. C.
20425 Radiochemistry & Nuclear Engineer-Division Decartment of Transoortation Nati onal Environmental Research C U.S. Environmental Protection Ace (Transmittal letter only)
Cincinnati, Ohio 45258
~
Office of Environmental Affairs U. S. Department ofTransportation Mr. Bruce Mann (1) 400 7th Street, S. W., 6.1G101 Naticnal Environmental Research-C-Washington,D. C.
20590 U.S. Environmental Protection Age-P. O. Eox 15027 (Transmittal latter only)
Las Vegas, Nevada Sglic cc:
Captain William R. Riedel Water Resources Coordinator Mr. Ellery Savage (1)
W/S 73 U.S.C.G., Room 7306 Eastern Environmental Radiation P U. S. Department of Transportation U.S. Environmental Protection Age-400 7th Street, S. W.
P. O. Box 3009 Washington,D. C.
20590 Montgcmery, Ala::ama 25109 E nvironmental P rotection A gency it. Neil ~homasson (i)
AT N: Loretto Long
.t. Tom J. Sharpe (1)
Cffice of Radiation Progra::s Division of Applied Technology U.S. Environmental Protection Age Cffice of Air Programs Waterside Mall, b. 54 7A E. Towe-U.S. Environmental Protection Agency 401 M St reet, S. W.
Research Triangle Park Washington, D. C.
20450 Durham, North Carolina 27711 4
s L
J.j
3 Environmental P rotection Acency Cont c.T (Coastal - salt water - only)
Dr. Eric 0. Schneider, Of rector (1)
National Marine Water Quality Laboratory U.S. Environmental Protection Agency South Ferry Road Narragansett, Rhode ' Island' 02882 EPA Recional Office U. 5. Environmental Protection Agency ATTN:
EIS Coordinator Region VI Office 1201 Elm Street Dallas, Texas 75270 Advisory Council on Historic P reservation Mr. Robert Garvey, Executive Directer (1)
Advisory, Council on Hi.storic Preservation 1522 K Street, N. W., Suit e 430 Washington, D. C.
20005 cc:
(Transnittal letter only)
Di rector Department of Natural and Cultural Heritage 7he Old Stone House 300 West Markham Little Rcck, Arkansas 72201 R
.w
Tr ENCLOSURE 6, RELEVANT DOCUFENTS ARXANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-368 FACILITY OPERATING LICENSE NPF-6 The_' documents listed below are relevant to plant operations subsequent to the issu.ance of NPF-6.. They will be prov.1ded to the Operator Licensing Project Manager, Operating Reactors Branch No. 4, on the date of the transfer memorandun.
1.
FSAR (Vols. I-IX) as revised through Amendment 46.
2.
SER, NUREG-0308 (November,1977)
(a) Supplement No.1 (June 1978)
~
( b) Suppl ement No. 2 (September,1978) 3.
Fi re ' Protection SER, NUREG-0223 (August,1978) 4.
Operating License NPF-6 and Amendments 1 through 12 thereto (July 18, 1978 to date of transfer memorandun), Vol.1.*
5.
Plant Technical Specifications, Appendices A & 3, and Amendments 1 through 12 thereto, Vol. 2.*
6.
Correspondence:
(a) Licensee to tRC ( August 30, 1978 to Novenber 30, 19 78 ), Vo l. 3.
- Licensee to NRC (December 11, 1978 to date of transfer memorandum),
Vol 4.*
(b) NRC to Licensee (September 29, 1978 to date of transfer memorandun),
Vol 5.*
(c) Interoffice Memoranda ( August 31, 1978 to date of transfer memorandun),
Vol. 7.*
(c) Inspection & Enforcenent Reports ( August 11,1978 o date of transfer memorand um), Vol. 8.*
s
.a~
t 2-(e) Licensee Construction Ceficiency Reports ( August 29, 1978 to date of transfer memorandun), Vol. 9.*
(f) Licensee Event Reports (kgust 30, 1978 to date of transfer memorandun),
Vol. 10.*
(g) Ponthly Operating Reports ( August 30, 1978 to date of transfer menorandun),
Yol 11.*
matecock vol une nunbers 9
1 e
112
- 42 1
O
,w-
.-w
.m..
4 ENCLOSURE 3
~
JUN 21lsp-:-
Cocket i:o. 50-368 f*E?:CRAt:DU:1 FCR: Cocc::ic'B. Vassallo, Acting Director fer.
Division of Project itanagccent FRCt!:
Daniel R. Muller, Acting Ofrector for Division of Site Safety and Environcental Analysis SU3JEC::
4RAi!SFER OF ARKA!iSAS l'UCLEAR Cf.'E, U !IT 2, TO CPERATI :G REACTORS BRAi:CH 4
!?e understand that you are planning to transfer Arkansas I:uclear One, Unit 2,'
frec CP?! to CCR. This cecorandum should be attached as an enclosure to ycur tran:for cecorandun to effect transfer of the enviNncental review res;:ensibilit; frec Envirencental Profects Granch 2 to Operating Reactors Granch 4.
This tran:fer of environcental respcnsibility is to be effective as of the date of
~
your transfer ceco.
The only item remaining to be ccrplated on this project is a recuest for change to the envirencental technical specifications dated ;;ay 10, 1979, which we will ec.;1cte.
At the tice of trcnsfer of responsibility, ISE, GT-:?A, and others on the distributien for this ceco shculd be notified of the following changes:
Frca To Envirer.cental Project i!anager D. Scaletti G.Ussing Branch Chief D. Sells
- R. Reid Assistant Director
- 11. Recan ti. Ganaill Licen:ing Assistant M. Duncan R. Ingraa Original signed by Daniel R. Mullec Pg;d np Canici R. ::uller, Acting Director for
~
[I)IP l [
Civisien of Site Safety and 011J Envirencental Analysis
@ dao m 79 1133 1 3
._