ML19209A191
| ML19209A191 | |
| 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 | |
| ML19209A188 | List: |
| References | |
| NUDOCS 7910030093 | |
| Download: ML19209A191 (25) | |
Text
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DISTRIBUTION:
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Docket File EHylton LShao OELO l
Ull NRC POR LEngle RVollmer ACM ORB #4 Rdg JStol:
TJCarter Reg. Files Meno File SVarga WRussell Public Info Prce Septecter 7,1979 NRR Rdg Dross R!ngram RCenise SWookey LWR Rdg File JKnight GVissing EGCase VMcore
'RReid HRDenten LShao WGannill OSS Docket No. 50-368 SGrimes 0Vassallo I&E (3)
JRMiller, COR DEisenhut MFA MEMORANDUM FOR: Carrell G. Eisenhut, Acting Director, Division of Operating Aeactors, Office of Nuclear Reactor Regulation FROM:
Domenic B. Vassallo, Acting Director, Division of Project Management, Office of Nuclear Reactor Regulation
SUBJECT:
TRANSFER OF ARXANSAS NUCLEAR ONE, UNIT 2 TO OrERATING REACTORS BRANCH NO. 4 Effective on the date of this memorandum, the safety project managerrent responsibility for Arkansas Nuclear One, Unit 2 is transferred from LWR Branch No.1, Division of Project Management, to Operating Reactors Branch No. 4, Division of Operating Reactors.
The 1f'ensee, Arkansas Pcwer & Lignt Company, received a facility operating license (NPF-6) on July 18, 1978. NPF-6 authori:ed the licensee to lead fuel and maintain the plant in Mode 5 (cold shutdcun condition).
Amencment No. I to NPF-6, issued on Septemoer 1,1978, authorized full power operation at 2815 MWt. Mcwever, the facility was temcorarily restricted from ocerating at full power until certain tests and other items noted in the license conditions were completed to the written satisfaction of IE and NRR.
Amendent No. 2 to NPF-6, issued on Septwter 22, 1978, temporarily suspended Tecnnical Specification 3.4.1 wnicn alldws only one hour operation without reactor core ficw in Modes 3, 4 and 5.
The temcorary suspension was granted for one 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> period valid througn October 9,1973, to allaw reL 4 rs to be c:moleted on a decay heat suction valve price to initial criticality.
Amendment No. 3 to NPF-6, issued on October 4,1978, revised Tecnnical Scecificaticn 4.6.4.3.5 to specify tha; :ne ficw rate for eacn of the containment recirculation fans be at least equal cc 4500 cubic feet per minute.
Amencment No. 4 to NPF-6, issued on October 17, 1978, corrected a typcgra;nical error in the Appendix 3 Technical Scecifications.
Amendment No. 5 to NPF-6, issued on Novemoer 13, 1978, modified tne Techniul 5:ecifications dealing witn :ne plant organizational struc:ure.
(The c:rrescending mecFications were also made to the 'Jnit 1 Tecnnial 5:ecificaticns).
7910 080 Ok 3 l
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0 P00R D E M Darmll G. Eisenhut Amendment No. 6 to NPF-6, issued on Novecter 18, 1978, provided one-time relief from Technical Specification 3.8.1.1.b to allow non-nuclear heatup operation within only one diesel generator and two offsite power systems available beforc repairs were completed on the second diesel generator which experienced mechanical fail 're on November 9,1978. The relief was granted foi no longer than three weeks from the date of issuance of Acendment No. S.
Amendment No. 7 to NPF-6, issued on December 1,1978, modified or removed three conditions to NPF-6 that had restricted the facility from going critical and operating at full power. Amendment No. 7 also modified or removed other license conditions involving acceptable completion of certain conduit penetration fire barrier testing; correction of an implementation date for an action required by the fire protection program; completion of acceptable changes needed for protec-tion from degraded offsite pcwer voltage; and modification of the tchedule for the remaining actions needed to complete the review of three core protection calculator system positions.
Amendment No. 8 to NPF-6, 4ssued 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 1 operating license).
Amendment No. 9 to NPF-6, issued on March 19, 1979, changed Technical Specification 3.5.1.4 by reducing the minimum initial containment temperature and pressure to 50 degrees Fahrenheit and a negative 3.0 pounds per square ince gauge, respectively.
Also, the steam generator low water level trip setpoint specified in Technical Specification Tables 2.2-1 and 3.3-4 was changed to a value of greater than er aqual to 46.5 percent.
Amencment No.10 to NPF-6, issued on March 30, 1979, temporarily suspended Technical Specification 3.6.1.6 which requires that the purge supply and exhaust system isol-ation valves be closed in Modes 1, 2, 3 and 4.
The temporary sugension was granted for one 30-hour period to allow two eight-hour purging operations in Modes 3 and 4 only.
t Amendment No.11 to NPF-6, issued on May 3,1979, modified the Appendices A and 3 Technic'il Specifications dealing with the licensee's management organization structure. (The corresponding modifications were also made to the Unit 1 Apnendices A and 3 Technical Specifications.)
Amencment No. 12 to NPF-6, issued on June 12, 1979, modified a condition te NPF-6 by removing the restrictions on making any software changes on -he core pro :ection calculator system based on our approval of the licensee 9 change :rocedures. Also, the Technical Specifications were changed to include a Near software Evgert as a memce of the licensee's Plant Safety Ccemittee. Amendment No.12 also removed anothe,' conditior regarding implementation of redundant valve position indication in the control room whicn had been verified to be ccmpleted in accordance with previously a: proved design modifications.
The current status of items requiring further staff action and tne organizations reponsible for completing nese items are identified in Enclosure 1.
Lists of generic proclems and regulatory guides used during the licensing review, with references to the locations unere relevant information or evaluations of record may be found, are included in Enclosure 2.
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P00R ORGINAL Darrell G. Eisenhut Enclosure 3 is a DSE memorandum which stm:tarizes the environmental status of the project and transfers the environmental project management resconsibi*ity from DSE to DOR. 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 subsequent to the issuance of NPF-6.
By copy of this memo, 055. IE, MPA, ELD, ADM, Regulatory Files, Public Information and Pubife Proceedings are being notified of the following safety personnel changes which are to be effective on the date of this memorandum. Enclosure 3 lists the environmental personnel changes.
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Project Manager L. Engle G. Vissing Branch Chief J. Stolz R. Reid Assistant Director S. Yarga W. Gamill Licensing Assistant E. Hylton R. Ingram
- j U
D menic 3. Vassallo, Acting Director Division of Project Management Office of Nuclear Reactor Regulation
Enclosures:
1.
Current Status of Items Requiring Staff Action 2.
Current Statue a# Generic Review Items 3.
DSE Transfer Memorandum 4.
Facility Service List
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Licensee's Distribution List 9,)4 6.
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1085 085
P00R0ItUIl'flg CURRENT STATUS OF ITEMS REQURING STAFF ACTION ARXANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-363 FACILITY OPERATING LICENSE NPF-6 The current status of the items requiring further staff action and the organizations responsible for completing these items are as follows:
1.
Fuel Perfornance License Condition 2.C(3)(a) stipulates that the licensee shall, prior to startup for the cycle of operation in which burnups greater than 20,000 megawatt days per ton of uranium are expected to be obtained, provide for Comission review and obtain Comission approval of revised fission gas release calculations and other affected analyses utilizing fission gas release calculational methodology approved for burnups greater than 20,000 megawatt days per ton of uranium. This matter is discussed further in Section 4.2.1 of Supplement No. 2 to the Safety Evaluation Report (SER).
The 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 matter will be performed by the Reactor Safety Branch (DOR).
Management responsibility for this matter will be carried out by Operating Reactors Branch No. 4 (COR).
2.
Instrument Trio Setcoints Drift Allowance License Condition 2.C(3)(d) stipulates that the licensee shall submit for Comission review certain infonnation for each reactor protection system and engineered safety feature instrumentation channel for incorporation in the Technical Specifications (TS). A document was suomitted by the ifcensee on February 28, 1979.
The Plant Systems 3 ranch (DOR) will maintain primary review responsibility for this matter. A SER for this review will be ccmoleted by J. Burdoin (PS3) prior to Novemcer 15, 1979. Management resoonsibility for this matter will be carried out by Coerating Reactors 3ranca No. a (CCR).
- 3. Jire Protection License Condition 2.C(3)(e), as modified by Amendment No. 7 to NPF-6 stipulates that the licensee shall comolete certain modifications by the indicated dates in accordance with our findings as set forth in NUREG-0223,
- Fire Protection SER. This matter is discussed further in Section 9.7 of the SER and Sucolement Un. 2 nereto.
Table 3.1 of NUREG-0223 is a sumary of the cu: standing items. MUREG-0223 recuires the licensee to suomit recuests for TS cnanges on items 3.5, 3.11, 3.ia ano 3.15 anc accitional infor.ation on items 3.6 and 3.7 at least 90 days prior to odifica:icn. adciticnal infor ation will be recuestec frca
- he licensee by CR5ea on items 3.a, 3.3, 3.9 anc 3.13 to allow comoletion af :ne review oracess. The 31 ant Systams 3rancn (:CR) will mainta'in
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2 primary review responsibility and will prepare the input to a SER within 30 days of receipt of the information on the aforemntioned items.
On Janus. 1 15, 1979, the licensee provided infomation to support the deletion of Item 3.10 from Table 3.1 of NURE 60223. The Plant Systems Branch (COR) is reviewing the status of this matter.
A letter from the licensee dated July 17, 1979 provides the latest status of completion of items listed 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-0?23, Table 3.1 Item 3.12 Fire Dameers On March 23-24, 1979 by telephone, and on May 1, 1979 by Licensee Event Report, it was identified that 32 fire dampers were not installed as required by architectural 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 request on April 17, sucolemented on May 18, 1979, for a modification to TS 3.7.11 to exemot four locations from the requirements of the TS until September 1,1979 wnen the damper installation is expected to be completed.
Tne Plant Systems Branch (00R) reviewed this request and submitted input to the SER. An amenc':nent will be issued by Operating Reactors Branch No. 4 (CCR) after receipt of the required input and concurrence from the Standard TS Group (CCR). The licensee has advised us verbally that the amendment request may be withdrawn since the damper installations will be completed shortly.
The Office of Inspection and Enforcement will verify that the modifications have been satisfactorily implemented. Management resconsibility for this matter will be carried out by Operating Reactors Branch No. 4 (DCR)-
4.
Ov.foressure Miticatine Svstem License Conditon 2.C(3)(f) stipulates that the licensee shall, prior to startuo following the first regularly scheduled refueling outage, achieve full imolementation of its proposed overpressure mitigating system described in the licensee's letter cated October 11, 1977. The licensee will submit a descriotion of the interlock or alarm to be installed on the isolation valves wnich will be reviewed by ICSB and RSB (DSS) to assure cono11ance with apolicable standarcs and criteria. RSB will orovide the input to an SER within 60 days of receipt of the infomation from the licensee.
The licensee will submit a recuest for a TS involving surveillance requirements for the relief valves.
he Plant Systems Branch (CCR) will be resconsible for :ne review. This matter is discussed further in Section 5.7 of Sucolement No. I to One SER.
The Office of Inspection and Enforcement will verify tha: :ne system has :een satisfactorily implementec. Vanagement.resconsibility for nis matter will ce carried out by Operating Reactors 3rancn No. J (:0R).
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0 P00R ORBK1 5.
Verification of Transient Analysis Code License Condition 2.C(3)(g) sticulates 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 Conn,tartup and power ission review and approval. This matter is discussed further in Section 15.4.2 of the SER and Supolement 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 Peactors Branch No. 4 (00R).
6.
Main Feedwater System Modifications License Condition 2.C(3)(h) stipulates that the licensee shall, prior to startup following the first regularly scheduled refueling outage, 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 6.2.1 of Sucplement No. 2 to the SER, and in an interoffice memo dated June 6,1979 from R. Boyd to H. Thornburg.
A TS surveillance requirement for the redundant main feedwater isolation valve may benecessary. The Plant Systems Branch (CCR) will review this matter and prepare the input to a SER including the evaluation of the changes tc TS.
The Office of Inscec: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 (COR).
7.
Containment Radiation Monitor License Condition 2.C(3)(i), as modified by Amendment No. 7 to NPF-6, stipulates that the licensee shall, prior to July 31, 1980, submit for Commission review and approval, documentation wnica establishes tne ade<;uacy of the cualifications of the containment radiation mcnitors located inside the containment and shall comclete the installation and testing of these instruments to demcnstrate that they meet the oceracility requirements of TS 3.3.3.6.
The Instrumentation and Control Systems Branch (DSS) will maintain primary review responsibility for this matter and will prepare the incut to a SER including the evaluation of the enanges to TS. "anagement resconsibility for :nis matter will be carried out by Ccerating Reactors 3ranen No. a '?OR).
S.
Core 3rotecticn Calcula:ce Svstem (C?CS)
Sue::ar:s (1), (2) and (3) of License Concition 2.C(3)(k), as modified by Amencments Nos. 7 and 12 to NpF-6, sticulate that the startup recor*; recuired by 75 6.9.1 ce succlemented to include :ne results of testing associated witn C?CS Position Nos. 1, 5 and 12, res;ectively. An interoffice memo f-cm S. Hanauer (055) on 1085 088
P00RORM1 April 6,' 1979 describes the Cemission's responsibilities relating to CPCS. A site visit is scheduled for September 13-14, 1979 by members of OSS.
(1) CPCS Position No.1, Power Distri0uticn Alcarithm Subpart (1) of License Condition 2.C(3)(k), as modified by Amendment No. 7 to NPF-6, stipulates that the startup report required by TS 6.9.1 be supplemented to include the results of the startup verification testing wnien 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.1 and 2 thereto.
The Core Performance Branch (055) 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 Performance Branch (DSS) is 1. Schere1.
In addition, the Plant Systems and Reactor Safety Branches (DCR) will monitor this matter in order to becoce knowledgeable about the CPCS.
D. Tondi and J. Beard will monitor this matter for the Plant Systems Branch and S. Weiss will monitor for the Reactor Safety Branch. Management responsibility for this matter will be carried out by Cperating Reactors Branch No. 4 (DCR).
(2) CPCS Position No. 5, Cable Secaration Subpart (2) of License Condition 2.C(3)(k), as modified by Amend: rent No. 7 to NPF-6, stipulates that the startuo report required by TS 6.9.1 be supplemented to include the results of measurements from the startuo testing program which demonstrate that noise or electromagnetic inter-ference effects from non-Class IE circuits which are in close ::roximity to Class IE circuits are within previously established acceptable ranges.
This matter is discussed further in Section 0.4.1.2 of the and Supplement Nos. I and 2 thereto.
The Instrumentation and Control System 3 ranch (OSS) will maintain ;:rimary review res;;cnsibility for this matter, and will precare the in:ut to a SER within 90 days of receipt of the testing re: ort. The assigned reviewer for this matter in the Instrumentaticn and Control Systems 3ranen is J. Joyce.
In addition, the Plant Systems Branch (DOR) will monitor this matter in order to bec0me knowledgeable about the CPCS.
D. Tondi and J. Seard will monitor this matter for the Plant Systems 3 ranch. Management responsibility for this matter will be carried out by Operating Reactors Brancn No. 4 (CCR).
(3) CPCS 30sition 'lo.12. Electrical Noise and Isolation Subcart (3) of License Condition 2.C(3)(k), as modiff ec :y kencment No. 7 to NPF-6, sti;:ulates that tne startuo recort re;uired by TS 6.9.1 be sucolemented to include the results of measurements from the startuo testing crogram wnicn demonstrate tnat noise or electromagnetic interference effects ucon ne ::ernien of the actical isolators are within oreviously estaoiisned accectacle ranges. This matter is discussed further in Sections 3.2.'.1 anc J.2.1.1 Of Su: clement Nos. I and 2 to tne SER.
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P00R D S M The Analysis Branch (DSS) will maintain primary review responsibility 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 Analys.is Branch is L. Phillips.
In addition, the Plant Systems Branch (DOR) will monitor this matter in order to beccme kncwledgeable about the CPCS.
D. Tondi and J. Beard will monitor this matter for the Plant Systems Branch. Management responsibility will be carried out by Operating Reactors Branch No. 4 (DOR).
9.
CEA Guide Tube Surveillance Procram License Condition 2.C(3)(1) stipulates that the licensee sh'alf, prior to startup folicwing the first regularly scheduled refueling outage, submit for Connission review and approval the results of a surveillance program conducted on the design modifications to the control element asswbly (CEA) guide tubes.
This matter is discussed further in Section 4.2.4 of Supplement No. 2 to the SER. The licensee will provide the surveillance program for review at least 90 days prior to shutdown for the first refueling.
The Reactor Safety Branch (DOR) will maintain primary review responsibility for this matter, and will approve the program and prepare the input to a SER on the results of the surveillance program. Management responsibility for this matter will be carried out by Operating Reactors Branch No. 4 (DOR).
10.
IE Bulletin No. 79-C6 On April 14, 1979, IE Bulletin No. 79-068 was transmitted to the licensee.
IE Bulletin No. 79-068 specified certain actions to be taken by the licensee to prevent the occurrence of an event stnilar to that which occur-red at Three Mile Island Nuclear Station, Unit 2 on March 28, 1979.
By letter dated Acril 24, 1979, the licensee provided its response to IE Bulletin 79-C68. Based on our review to date of the inferr.ation provided by the licensee, we have concluded that, while we have identified certain areas in whicn additional action or information is needed, the licensee has correctly interpreted IE Bulletin No. 79-068. The 1fcensee has stated that no changes to the TS are required at this time in response to the actions required by IE Bulletin 79-068.
A request for additional infor nation was issued on July 25, 1979, with re-sponse requested by August 10, 1979. The assigned project manager is I. Villalva.
On July 26, 1979, IE Bulletin No. 79-C6C was transmitted to the licensee.
IE Bulletin No.79-06C specified long and short term actions to be taken in arcer to alleviate the concern over delayed tripping of :ne RCPs after a LCCA.
The res::ense to Bulletin 79-C6C is not yet availaole, but will be co-ordina:ed by I. Villaiva.
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P00RORSNAL Further staff actions required as a result of IE Sulletin 79-06 will be carried out as a joint effcrt between the Bulletins and Orders Task Force and 00R. Bulletins and Orders Task Force will have primary management responsibility for this item.
- 11. TMI-2 Generic Review of Coerating CE plants As a result of the accident at TMI-2, the licensees of plants utilizing Combustion Engineering nuclear steam supply systems have fc.med an cwner's group to address certain TMI-2 related matters such as our request for additional information concerning small break loss-of-coolant accident analyses. Our stipulation for this study is documented in our letter to the licensee dated June 5, 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 cer@lete our generic evaluation for Combustion Engineering plants.
Further staff actions required as a result of this matter have been assigned ta the Bulletins and Orders Task Force. COR will interface witn the Bulletins and Orders Task Force as necessary for any plant specific actions that might be required in the future, i2. EFW Pumo Resconse 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.
DCR 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 (CRBd4).
- 13. Asynretric Bicwdown Leads on Reactor Primary Ccolant Systems - pWR Reactor vessel supports and reactor internals are discussed in the SER pp. 3-17 through 3-19 in Supplement 2 pp. 3-1 and 3-2, and in a submittal frca the licensce on January 17, 1978.
S. Hosford (E3) is the task coordinator. The Analysis Branch (DSS) is responsible for the site specific comparison between the CENp0-42 vs. CEFLASH-48 medels. The task coordinator will infom CRB!4 of the outstanding items concerning this issue prior to August 24, 1979.
Management responsibility for this matter will be carried out by CRS#a.
la.
Containnent Leak Testina - Accendix J Apcendix J recuirements are discussed in the SER p. 6-7; Sucolement 2 pp. 5-6 and 6-7 and in the TS pp. 3/4 6-2 through 5-5.
Amendment ':c. I to the Cperating License NPF-6, issued Septemcer 1,1973, authori:ed a
- nree year exemotien regarding testing of rimary :entainment air locks.
G. Arndt (SCSB) is involved in the deveicement of a general exemption regarding containment leak testing wnicn sncuid te resol ved price o - e time wnen :ne licensee's exemption expires.
- CR revia responsibility will be assigned as necessary in accordance with cutine procedures. Management resconsibility for this matter wi!! be carried out by CR3=a.
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- 15. Diesel Generator L;ck-Out (3-1)
A generic letter was issued on November 11, 1977, to which the licansee responded on December 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 CRBd4 within 30 days of the receipt of the information.
Management responsibility will be carried cut by 0"2e4.
16.
Inservice Testine - Pumos and Valves Inservice testing is addressed in the SER p. 3-16, Supplement 2 pp. 5-1 and 5-2, TS 3/4-02, 3/4-03 and 3 3/4 0-3.
The Mechanical Engineering Branch (CSS) will-maintain primary review responsibility for this matter.
055 will be contracting the review of the licensee's testing program, through the Department of Energy, with the Idaho National Engineering Labcratory (INEL).
H. 3ramer (MES) will inform ORBf4 f f 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 Supplement 2 p. 5-2, the acceptability of the licensee's program is to be detemined prior to the start of facility comercial operation (approx.
9/20 to 9/25/79). Adequate comunication is required between all parties aforecentioned to insure that timely alternatives are available due to the fact that the ccntractor's review will not be ccepleted prior to the licensee's comercial operatica date.
1.'. Leaxace of Cantainment Isolatien Valves with Resilient Seats This generic issue (3-20) is based upon -IE Circular 77-11 issued in Septemcer 1977. The lead engineer en this generic i:ssue is C. Grimes of the Plant Systems 3 ranch (CCR). Action on this issue is being held pending resolution of generic item 3-24 relating to venting and purging containments while at full power. Management responsibility will :e carried out by CRS*J wnen the issue is reccened.
13.
PWR Secondary Water Chemistry Menitorinc Recuirements This issue is addressed in the SER p. 5-11 ane TS pp. 3/4 7-11 through 3/4 7-12.
By letter from the Comission dated August 2,1979, the licensee was requestad to submit within 50 days a precosed amendment to license NPF-6 that will include the seconcary water enemistry program.
The orogram will be referenced in a condition to the license and will replace the existing TS On secondary water chemistry.
Management res:ensibility for the ccification to the license will :e carried out cy ORE =4 1085 092
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- 19. Pumo Succort - Lamellar Tearinc [ Fracture Touchness] (C-6)
A generic letter was issued on Decemoer 5,1977, to which the licensee responded on December 19, 1978. A NUREG will be issued in September 1979 cn this generic issue. The licensee's specific review,'will be performed by a contractor. The Engineering Branch (DOR) is responsible for the supervision of the contract. This generic issue is to be completed by 1982.
Management responsibility will be carried out by ORBr4 9
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P001 D U M
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ENCLOSUREj CURRENT STATUS OF GENERIC RF'/IEW ITEMS ARKANSAS NUCLEAR ONE, UNIT 2
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The current status of tire generic review items are listed below. Except for the regulatory guides, the generic review items correspond to those listed in the ONRR Operating Reactors Licensing Sumary (COR Generic Issues).
A.
Items which have been resolved and require no further NRC action:
Item Reference 1.
ECCS Evaluation SER p. 5-10; Suppl. 2 pp. 6-7 throuch 6-9 (A-8)
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2.
Effluent Treat:nent Systems SER pp.12-1 through 12 4 (ALARA) (A-2) 3.
Emergency Planning SER pp.13-3 & 13-4; Suppl. 2 p.13-1 (B-16) 4 Filter Tech Specs TS pp. 3/4 7-17 thrcugh 3/4 7-19 (C-4) 5.
Floed of Equipment Important SER pp. 6-10 & 10-2; Suppl. 2 pp. 6-7 & 6-10 to Safety (B-ll) 5.
Fracture Toughness Requirements SER pp. 5-2 & 5-3; Suppl. 2 p. 5-1 Appendix G (A-7) 7.
High Energy Line 3reak SER pp. 3-7 througn 3-9 3.
In-Reactor Growth of CE Scop 1. 2 p. 4-1
?oisen Reds 'B-15) 9.
Inservice Inspection of ?%R SER pp. 5-11 & 5-12; TS pp. 3/4 4-6 througn Steam Generator Tubes 3/4 4-12 (3-12)
- 10. Qualifications of Radiation SER pp.13-1 1 13-2; TS pp. 5-1 thrcugn 5-5 Protection Manager (C-3)
- 11. Resoiratory Protection Program (A-6)
- 12. Steam Generator Feedwater Flow Instability (3-7) 13.
?otential Equipment Failure SER p. 3-2; Sucpl. 2, pp. 3-1 & 3-2; 'GF-Associated With Cegraded Grid Condition 2.C(3)(0) as redified by
'loi tage (3-23)
Amendment No. 7.
1085 094 REGULATORY GUIDES 14 Net Position Suction Head for SER pp. 6-4 & 6-9 Emergency Core Cooling and Containment Heat Removal System Ptmps (R.G.1.1) 15.
Assumptions Lied for Evaluating SER p. 2-11 the Potential Radiological Consequences of a loss of Coolant Accident for Pressurized Water Reactors (R.G.1.4) 16.
Inde;endence Between Rendundant SER. pp d-l & 8-3 Stancby (Onsite) Power Sources and Between Their Distribution Systems (R.G.1.6) 17.
Control of Combustible Gas SER pp. 6-6, 5-7 & 6-15; Suppl. 2, p.15-6 Concentratiens in Containment Following a Loss of Coolant
- ccident (R. G.1.7) 18.
Persennel Selection and Training SER pp.13-15 13-2 (R. G. 1.3 )
19.
Selection of Diesel Generator Set SER pp. 8-1 3 3-3 Capacity for Stancby Power Supplies (R.G.1.9) 20.
Instrumentation for Earthquakes SER p. 3-10 (R. G. 1.12 )
21.
Spent Fuel Storage Facility SER pp. 3-6, 9-2, 9-3 & 9-4 Cesign Basi s (R.G.1.13 )
22.
Reacter Coolant Pump Flywheel SER pp. 5-9 3 5-10 Integrity (R. G.1.14) 23.
Protection of itclear Powr SER p.13-5; Suppl. 2 p.13-1 Plants Against Incustrial Sacotage (R.G.1.17 )
24.
Structurai k:eptance Test for SER p. 3-11 Concrete Primary Reactor Containments (R.G.1.13 )
1085 095
. 25. Comprehensive '.ibration Assess-SER p. 4-5 ment Progrr. for Reacter InternC3 During Preoperational an'. Initial Startup Testing (R. G. 1. 20 )
- 25. Measuring, Evaluating, and SER pp.11-5 & 11-6 Reporting Radioactivity in Solid 'Aastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light ' Water-Cooled Nuclear Pour Plants (R.G.1.21)
- 27. Cnsite Meteorological Programs SER pp. 2-11 & 2-12 (R. G. 1.23 )
- 28. Assumptions Used for Evaluating 52r, p.15-17 the Potential Radiological Consequences of a Fuel Pandling A:cident in the Fuel Handling and Storage Facility for Sciling aM Pressurized ' dater Reactors (R.G.
1.25 )
- 29. Ultimate Heat Sink for lbclear SER p. 9-6 Power Plants (R.G.1.27 )
- 30. Seismic Cesign Classification SER pp. 9-2, 9-10 & 10-2 (R. G. 1. 29 )
- 31. Criteria for Safety-Relateo SER p. 8-1 Electric her Systems for Nuclear Power Plants (R. G. 1. 22 )
- 32. Nonmetallic Tnermal Insulation SER ;p. 5-4, 5-7 & 5 - 15 for Austenitic Stainless Steel (R. G. 1.26 )
- 33. Cuality Assurance Requirements SER p. 5-7 for Cleaning of Fluid Systems and Associated "om;cnen s of
'4ater-Coolec Nuclear Pcwer Pl ants (R.G.1.37 )
1085 096
P00R ORGINAL
- 34. Preoperational Testing of SER p. 8-1 Redundant Cn-Site Electric Power Systems to Verify Proper Load Group Assignments (R. G. 1.41)
- 35. Control of the Use of Sensitized SER pp. 4-5, 4-6, 5-5, S-6, 5-7 & 6-14 Stainless Steel (R.G.1.44)
- 36. Reactor Coolant Pressure Boundary SER p. 5-9 Leakage Catection Systems (R. G. 1.45 )
- 37. Protection Against Pipe Whip SER pp. 3-7 & 3-8 Inside Containment (R.G.1.46 )
- 38. Bypassed and Inocerable Status SER p. 7-19 Indication fcr Nuclear Power Plant Safety Systems (R.G.1.47)
- 39. Cesign Limits and Loading Com-SER pp. 3-16 & 5-1 binations for Seismic Category I Fluid Systen Components (R. G. 1.48 )
- 40. Control of Preheat 7emperature SER pp. 5-6 & 5-7 for Weiding of Low-Alloy Steel (R. G. 1.50 )
- 41. Design Sasis Floods for tbclear SER p. 3-13 Po wer Pl ant s (R. G. 1. 59 )
- 42. Camping Values for Seismic Cesign SER p. 3-9 of Nuclear Power Plants (R. G. 1.61)
- 43. Installation of Cveroressure SER pc. 3-17 & 5-2 Protecticn Cevices (R.G.1.67) 44 Initial Test Programs for Water-SER p.14-1 Cooled Reacter Power Plants (R. G. 1. 68 )
- 45. Assumptions Used for Evaluating SER p.15-11 a Control Roc Ejection Accident for Pressurized Water Reactors (R. G. 1. 77 )
1085 097
P00R ORBM
-e-46.
Preoperational Testing of Emer-SER pp. 6-12 & 14-2; Suppl. 2 p 14-1 gency Core Cooling Systems for Pressurized Water Reactors (R. G. 1. 79 )
- 47. Inservice Inspecticn of Pressur-SER p. 5-12 i:ed Water Reactor Steam Generator Tubes (R.G.1.83)
- 48. Code Case Acceptability-ASME SER p. 2-3 Section III Design and Fabrication (R.G.1.84)
- 49. Coce Case Acceptability-ASME SER p. 3-2 Section III Material s (R.G.1.85)
- 50. Protection of f.bclear Power SER p. 6-14 Plant Centrol Rocm Cperators Against an *ccidental Chicrine Release (R.G.1.95) 51. Methods for timating Atmos-SER pp. 2-11 & 2-12 pheric Trsnsport and Dispersion of Gasmos Effluents in Routine Releases fra Light Water C:cled Reacters (R.G.1.111) 52.
Fire Protection Guidelines for SER p. 9-11 Nuclear Powr Plan s (R.G.1.120) 53.
Informatien Relevant to Maintain-SER p. 12-1 ing Cccc:atenal Radiation hpcsure as Lcw as is Reascnably Achievable (Nuclear Power Reactors) (R.G. 8.8) 54 Ocerating Philosophy for Maintain-SER p.12-1 Cccucational Radiation Spesures as L w as is Reasonacly Achievable (R. G. 8.10 )
108$
098
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8.
Itams which have been evaluated in licht 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 - 1.one Term Procram A meeting with Combustion Engineering will be he d 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 Commission by the spring of 1980. Site Specific requirements should be available by the sunner of 1980.
A. Thadani (055) 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 Bow Effects (00R Generic Issue 8-13)
This issue is discussed in the SER pp. 4-15 and 4-16 and in Supplement No. 1 pp. 4-1 and 4-2.
This facility is the first to use Combustion Engineering's 16 x 16 fuel assemblies. Following the first cycle of operation, reanalyses along with red bow measurements submitted by the licensee or fuel vendor will be reviewed by the Reactor Safety Branch.
Management responsibility will be carried 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 0.
Items of which their status needs further review or clarification.
The Division of Operating Reactors will assume primary review responsibility for these items. Management responsibility will be carried out by Operating Reactors Branch No. 4.
1085 099
e P00RORGNAL e Item 1.
Generic Issues (ONRR Operating Reactors Licensing Sunnary)
A-2 Appendix I - ALARA A-9 Pressure Vessel Beltline Material Surveillance A-10 Contingency Planning A-11 Guard Training Plans A-12 Vital Area Analysis B-3 Moderator Dilution B-8 PWR HPSI-LPSI Flow Resistance B-9 Charging Systems Pipe Vibrations B-17 Technical Specifications Surveillance for Hydraulic Snubbers B-21 Loss of 125-V DC Bus Voltage With Loss of Annunciation System S-22 Technical Specification Surveillance Recuirements for Mechanical Snubbers B-24 Venting and Purging Containments While at Full Power and Effect on LOCA 3-26 Inadvertant Safety Injection During Cooldown B-36 Resistance Temperature Cetector (RTD) Rcsponse - CE S-37 Steam Generator Tube Centing and Suppor Plate Modifications - CE B-39 PWR Pressure-Temperature Limit Technical Specificaticns B-41 Fire Protection - Final Technical Specifications (Including SER Supplements) t C-7 Fuel Handling Accident Inside Containment C-12 Baron Solubility During Long Term Cooling Following LOCA D-4 PUR Reactor Vessel Cavity Seal Ring Missile Potential D-6 Peaking Model Change for CE Reactor Core D-3 Jeficiency in Chem. Addition to Containment Sprays E-i Spent Fuel Fool Expansions E-3 Core Reloads Requiring Prior.1RC Approvai E-6 CEA Position Incication Failures - CE E-7 Reactor Protection System Logic - CE Cracking in Feecwater Lines - ?WR 1085 100
P00RORGNAL
~ E.
Items which are not applicable to ANO-2.
Item R e'ference 1.
ATkS - Short Term Progr:m (Cat B BhR 's) 2.
Bh2 Safety-Relief Valve Surveillance 3.
ECCS Reevaluation to kcount for Increased Vessel Head Fluid Temp 4.
Mark I Contaircent - Short Term Program Technical Specifications 6.
Mark I Contaircent Evaluation Long Term Program 7.
Mark I Safety / Relief Valve Line Restraints in the Torus 8.
Non-Jet Pump (flJP) ShR Core Soray Cooling Coefficients 9.
Powr Level for RWM Cperability 10.
Pressurizer :-eatup Rate-Westinghouse PkR' s
- 12. Westingneuse Error in Metal-Water Reaction Calculation
- 13. Westingr.cuse Lbcer Plenum ECCS Injection - L:ng Range 1085 101
JUN 2.3.197L -
Occhet llo. 50-360
!:E :CRAT:CU:1 FCR: Ccc=ic B. Vassallo, Acting Director for Divisica of Project itanacccent FRC?i:
Daniel R. !!uller, Acting Director for Division of Site Safety and Envire= ental Analysis SUSJECT:
TRAi!SFER OF ARKA;iSAS i:UCLEAR CI:E, U:!IT 2, TO CPERATII:G REACTORS BRAI:CH 4
!?e understand that you are planning to transfer Ar.::ansas I:uclear One, Unit 2, ~
frca CPit to CCR. This cocorandum should be attached as an enclosure to ycur transfer cc crandun to effect transfer of the envirenecntal review responsibilit frca Envirennental Projects Granch 2 to Operating Reactors Sranch 4 This tran:for of environcental res;cnsibility is to be effective as of the date of your transfer caco.
The enTy item remaining to be cc. pieted en this prcject is a recuest for change to the envirencantal technical specificaticas dated fiay 10, 1979, v:hich tie will complete.
At the t1cc of transfer of respcasibility, ISE, 0"PA, and others en the distributien for this ceco shculd be notified of the following changes:
From o
Environmental Project -fanager D. Scaletti G. Vissing Branch Chief D. Sells R. Reid Assistant Director
- 11. Regan ti. Garcill Licensing Assistant fi. Duncan R. Ingrca original signed by Daniel R. Muller Daniel R. :uller, Acting Director for Division of Sita Safety and Envirenccntal Anclysis 1085 102
ENCLOSURE 4 FACILITY SERVICE LIST ARXANSAS NUCLEAR ONE, UNIT 2 DOCXET NO. 50-368 FACILITY OPERATING LICENSE 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 Pope County Judge Arkansas Power & Light Company Pope County Courthouse P. O. Box 551 Russellville, Arkansas 72801 Little Rock, Arkansas 72203 U. S. Environmental Protection Philip K. Lyon, Esq.
Agency House, Holmes & Jewell ATTN: EIS Coordinator 1550 Tower Euilding Region VI Office Little Rock, Arkansas
- 72201, 1201 Elm Street Dallas, Texas 75270 Mr. E. H. Smith, Project Engineer Bechtel Power Corporation Mr. James F. O'Hanlon San Francisco, California 94119 General Panager - Arkansas Nuclear Cne Fr. Fred Sernatinger, Project Manager P. O. Box 508 Combustion Engineering, In'c.
Russellville, Arkansas 72501 1000 Prospect Hill Road Windsor, Connecticut 06095 Mr. Charles S. Brinkman, Manager Washington NJclear Coerations C -E Po wer Syst ems Combustion Engineering, Inc.
4853 Cordell Avenue, Suite A-1 Sethesda, Maryland 20014 Mr. E. F. Wilson, Cirector Bureau of Environmental Health Services 4815 West Marknam Street Little Rock, Arkansas 72201 108S \\03
--m
a.
ENCLUSURE 5 LICENSEE S DISTRIBUTION LIST ARKANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-368 FACILITY OPERATING LICENSE NPF-5 Acolication, General Information and Safety Analysis Recort and Arendments Mr. E. F. Wil son, Di rector Bureau 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 Protection Agency ATTN: EIS Cordinator Region VI Office 1201 Elm Street Dallas, Texas 75270
~
Environmental Recort and Amencments and Succlemdnts (Numoers in parentneses indicate numoers of copies)
Decartment of Commerce Decartment of I nterior Cr. Sidney R. Galler (5)*
Mr. Bruce Blanchard, Director (18)
Deputy Assistant Secretary for Office of Environmental Projects Environmental Affairs Review, Room 5321 U. S. Department of Commerce U. S. Department of Interior 14th & Constitutien, N. W., Tc. 3425 18th & C Streets, N. W.
Wasnington, D. L.
20230 Washington, D. C.
20240 Mr. Robert Ochinero, Direc*or (1) cc :
(Transmittal letter only)
National Cceanographic Cata Center Chief Environmental Data Service Division of Ecological Servicer National Cceanic and Atmospheric Sureau of Soort Fisheries &
Acministration Wildli fe U. S. Cepartment of Commerce U. S. Cesartment of Interior Washington, D. C.
20235 18th & C Streets, N. W.
Washington, O. C.
202:0
' Generic - 13 copies Amencments - 5 copies 1085 104
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P00R ONL
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Decartment of HEW Environmental P rotection Agency (C ont' c )
Mr. Charles Custard, Director (2)
Office of Environmental Affairs Mr. Devereaux Barnes (1)
U. S. Department of Fealth, Education Effluent Guidelines Division and Wel fare, Room 4740 U.S. Environmental Protection Age-330 Independence Avenue, S. W.
Waterside Mall, Rm. 905 E. Tower Washington, D. C.
20201 401 M St reet, S. W.
Washington, D. C.
20460 Federal P cwer Ccemission Ms. Geraldine Verdig (1)
Chief (1)
Environmental Evaluation Branch Bureau of Power Office of Water Programs Federal Power Commission, Rn. 5100 U.S. Environmental Protection Age 825 North Capitol Street, N. E.
Wa terside Ma ll, Rm. 2818 E. To wer Washingten, D. C.
20426 401 M Street, S. W.
Washington, D. C.
20460 Federal Power Ccamission, Rn. 6100 (1) 825 North Capitol Street, N. E.
Dr. Bern Kahn (1) -
Washingten, D. C.
20426 Radiochemistry & Nuclear Enginee.-
Division Decartment of Transecrtation National Environmental Research C-U.S. Environmental Protection Age-(Transmittal letter only)
Cincinnati, Ohi o 45268 Of fice of Environmental Affairs U. S. Departnent ofiransportation Mr. Bruce Mann (1) 400 7th Street, S. W., Rn.10101 Natienal Environmental Research-Cs Washington, D. C.
20590 U.S. Environmental Protection Age-P. O. Box 15027 cc:
(Transnittal latter only)
Las Vegas, Nevada 89114 Captain William R. Riedel Water Resources Coordinator Mr. Ellery Savage (1)
W/S 73 U.S.C.G., Rcom 7306 Eastern Environmental Radiatic.
n M. -
U. S. Department of Transportation U.S. Environmental Protection fx 400 7th Street, S. W.
P. O. Box 3009 Washington, D. C.
20590 Montgcmery, Alabama 56109
- '{. u n.-
E nvironmental P rotection A gency Mr. Neil Thoma: son (1)
. g.'
ATTN: Loretto Long
.,<d Mr. Tom J. Sharpe (1)
Office of Radiatien Progra.
.t.
sq Division of Applied Technology U.S. Environmental Protectn... 3e r
Office of Air Prograns Wat rside Mall, Rn. 64 7A -
To me -
U.S. Environmental Protection Agency 401 M St reet, S. W.
Research Triangle Park Washington, D. C.
2046C Curnam, North Carolina 27711 i
1085
~,.,a
-w
-~m-
4.
~
P00R ORGINA
~
E nvironn enta' P rotection A cency (Cont'd.
(Coastal - salt water - only)
Cr. Eric D. Schneider, Director (1)
National Parine Water QJality Laboratory U.S. Environmental Protection Agency South Ferry Road Narragansett, Rhode Is1and 02882 EPA Regional Office U. S. Environrnental Protection Agency ATTN: EIS Coordinator Region VI Office 1201 Elm -Street Dallas, Texas 75270 Advisory Council on Historic P reservation Pr. Robert Garvey, Executive Director (1)
Advisory. Council on Historic Preservation 1522 K Street, N. W., Suite 430 Washington, D. C.
20005 cc:
(Transmittal letter only)
Di rector Department of Natural and Cultural Heritage The Old Stone House 300 West Markham Little Rock, Arkansas 72201 1085 106
?
j" ENCLOSURE 6 RELEVANT DOCUFENTS ARKANSAS NUCLEAR ONE, UNIT 2 DOCXET NO. 50-358 FACILITY OPERATING LICENSE NPF-6 The doctments listed below are relevant to plant operations subsequent to the issuance of NPF-6.
They will be provided to the Operator Licensing Project Panager, 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) Supplement No. 2 (September,1978) 3.
Fire Protection SER, NUREG-0223 (August,1978) 4.
Cperating License NPF-6 and Amendments 1 through 12 thereto (July 18, 1978 to date of transfer memorandua), Vol.1.*
5.
Plant Technical Specifications, Appendices A & S, and Amencments 1 througn 12 thereto, Vol. 2.*
6.
Correspondence:
(a) Licensee to tRC (kgust 30, 1978 to Novemoer 30, 19 78 ), Vol. 3.
- Licensee to NRC (Cecember 11, 1978 to date of transfer memorandum),
Vol 4.*
(c) NRC to Licensee (September 29, 1978 to date of transfer memorandun),
Vol 5.*
(c) Interoffice Memoranda ( August 31, 1978 ta date of transfer memorandun),
Vol. 7.*
(c) Inspection & Enforcement Reperts (kgust 11, 1978 to date cf transfer memoranc um), Vol. 8.*
1085 107
~
~
(e) Licensee Construction Deficiency Reports ( August 29, 1978 to date of transfer memorandun), Vol. 9.*
(f) Licensee Event Reports ( August 30, 1978 to date of transfer memorandun),
Vol. 10.*
(g) Mwtnly Operating Reports ( August 30, 1978 to date of transfer menorandun),
Vol 11.*
- tet eoco A vol une nunbers 1085 108
_.