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1%, UNITED STATES f[T o NUCLEAR REGULATORY COMMISSION a wassiNoTON, D. C 20555 gh ,
+ November.3, 1983
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NOTE T0: ,ORBf2'IProject Managers' Division of Licensing' .
.. FROM: Domenic B. Vassallo, Chief
- < . Operating Reactors Branch #2 .
F- . Division of Licensing
SUBJECT:
(GENERIC LETTER 83-28) REQUIRED ACTIONS BASED ON GENERIC IMPLICATIONS OF SALEM ATWS EVENTS Licensees were given until November 5,1983(120 days a~fter issuance -
of 83128 on July 8,'1983) to respond. PMs are requested to provide a copy of their licensee's response to ORAB (Tom Alexion or John Zwolinski).
Thanks.
l Domenic B. Vassallo, Chief Operating Reactors Branch #2
,, Division of Licensing l
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T) lD E. REFERENCES
- 1. 09-06-83: Requested Extension to April 84 to respond to this letter based upon BECo participation in industry programs.
- 2. 10-19-83: Request was denied by the NRC; requested BEco to submit the information to the extent practical, provide conenitments and schedules for items where final implementation is known and to supply our plans and schedules for developing programs where needed.
- 3. 11-07-83: BEco submitted Respnnte to EL 83-28. Addresltd til the items, excluding NUTAC (VIP) report.
- 4. 04-27-84: BEco submitted Response to EL83-28 Vendor Interface Program endorsing NUTAC/VETIP programs (except for item 3.2 of the NUTAC report which deals with enhancements in NPROS). BEco conreitted to implement those items of the VETIP which are/will evaluated to be beneficial.
- 5. 07-09-84: SEco submitted response to EO-SER stating that a e centralized VETIP will be implemented to enhance interf ace between utilities and the NSSS Vendor and the 'as needed' interface with other vendors.
- 6. 04-23-85: NRC Requested Additional Information (RAI) on Items: 2.1, 2.2.2, 3.1.3, 3.2.3 & 4.5.3. Requested Information within 60 days f rom the receipt of the letter.
- 7. 06-28-85: BEco Response to RAI of April 23, 1985 stated that:
a) we are evaluating VETIP to implement the beneficial items of MUTAC Report, b) provided response to all but Item 4.5.3
- 8. 06-17-85: NRC RAI on Post-Trip Review. Requested to provide information and reissue PTR procedure.
- 9. 08-13-85: SEco submitted Response to RAI of June 17 1985 provided PTR procedure 1.3.31
- 10. 09-11-85: NRC Letter on PTR Item 1.1 of GL 83-28 issuing 1[2 stating PTR is acceptable.
- 11. 08-23-85: SEco submitted Response to item 4.5.3 regarding back-up scram valves - BEco said no testing of back-up scram valves is needed as a result of BWROG Report on Scram Reliability.
- 12. 04-22-86: NRC 1etter on Itetts 3.1.3 and 3.2.3 - stating that BEco's Response is acceptable.
- 13. 02-18-86: Telephone call regarding 6L 83-28 Items 3.1.1 and 3.1.2 -
. Requested clarification on Post Maintenance Testing for Safety-related Items.
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- 14. 04-25-86: 8Eco previded clecification as requested above.
- 15. 01-17-86: NRC issued Technical Evaluttion Report on Post-Trip Review Data - Requested telecon is suf ficient to resolve this issue.
- 16. 02-26-86 BEco add-sssed the Post-Trip Review Data TER in a telecon and closed the items. BEco said we will be witing to review t.te SER. (SER has not yet been issued.
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Eclison COV3AV NUC1. EAR 0?IRATIONS DEPARDENT
?ILGED! NUCLEAR POWER STATION Procedure No. 1.3.33 I REVIE*=' AND ASSESS >ENT OF OPERATING EXPERIEN3 i
List of Effective Pages 1.3.33-1 1.3.33-2 1.3.33-3 1.3.33-4 1.3.33-5 1.3.33-6 Attachments 1.3.33A-1 1.3.33B-1
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Approved I, f (,)/ -
ORC, Chairman Date u '. ~> S/ / . 2 1.3.33-1 Rev. 1 ,
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l I. PURPOSE The purpose of this procedure is to establish methods whereby the On Site Safety and Performance Group (OSS&P) in conjunction with the Plant Operating Experience Assessment Committee (POEAC) reviews;-
assesses.and makes recommendations to various departments within the Nuclear Organization based on operating experience information per-tinent to plant safety originating outside Boston Edison Company.
The functions to be accomplished through this procedure are:
A. To identify organization responsibilities for the review of information from outside Boston Edison Company which could be _
pertinent to plant safety. Information originating inside Boston Edison Company is dispositioned under existing work control.
processes unless specifically referred to the OSS&P Group by the ORC.
- 3. To define and track the course of action resulting from such reviews.-
C. To assure that reviews are incorporated into procedures and training programs or forwarded for information.
D. To establish periodic internal audits of the review process to
{ ensure its proper performance.
II. APPLICABILITY This procedure applies to the Nuclear Operations Departaant, the Nuclear Operations Support Department and to the Nuclear Engineering
- Department for assistance in the assessaant of opers. ting experience; to the Information Resources Management Group and the Planning and
~
Scheduling Group for cracking them through the review and assessment; and to the -ceivr,s.of information via the operations feedback procedure.
III. PRECAUTIONS -
A. This procedure is not intenddd to preclude the normal routing of infornstion for training.
- 3. This procedure is not intended to preclude the current methods of routing and obtaining action on documents from licensing such as the Bulletins NUREG requirements, etc.
IT. REFERENCES A. . NRC 1ask Action Plan. Ites I.C.5. " Procedures for Feedback of Opersting Experience to Plant Staf f."
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.- V'. DEFINTIONS l A. Similar - Performing an identical function when compared with PNPS 1.
B. Close-out - A disposition given to information which indicates that no other actice is required.
VI. RESPONSIBILITIES A. On Site Safe T and Performance Group To administer the overall program for review and assessment of operating experience, including performing the following functions: screen operating experience items, coordinate and interf ace with the POEAC to recommend dispositio and close-out of items. maintain index and status of reviewed items. participate in " Note Pad" for Boston Edison at Pilgrim Station.
B. Plant Operating Experience Assessment Committee (The membersi-ip of this committee vill be comprised of representatives from vario:s Suclear Organization Departments, collectively experienced in the folleving fields: Operations, Nuclear Safety, Nuclear EnF'reering.
Elf.ctrical. 3strumentation and Control and Mechanical Maintenance).
To review cperating information, determined to be significant to Pilgrim by the screer_ing process, and to recommend disposition of such items to responsible d.epartments or individuals.
C. Nuclear Entimeering Department To perf orm technical assessments of specific external information as requested by the OSS&P Groups or the POEAC.
D. Inf ormatio- 3.esources Management Group To ensure that OSS&P Group receives external documents, to provide controlled transmittals of specified documents and maintain records of documents which are closed-out.
E. Planning a:d Scheduling Group To track opem items requiring action by other departments / individuals to ensure itens are captured under existing work control processes.
F. Quality Assurance Department To annually audit this program to ensure the objectives of the procedure are being net. l I
G. Department s /hdividuals Groups or individuals receiving action items or inf ormational transmittals are responsible for responding as specified.
H. Training Department i The POEAC and OSS&P Group will make recommendations to the Training Department f er incorporation of Opcrating Experience Inf ormation into l i
1.3.33-3 Rev. 1
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trotning Apf 1pt*.(ah;hy pICfgIs! fht. Mig!M *Qpdgigt.mef/ vil,4 *afsd0 ths e to which to incorpar.sto the tif or-information and datormin2 th2 extent mation into training and retraining programs.
' PROCEDURE VII.
A. Internal Information The Operations Review Committee (ORC) is primarily responsible ef re-viewing internally generated documents and determining their disposition.
Internal inf ormation requiring some kind of f ollow-up action (i.e. .
procedure change, design change) is typically contro11ed' us follow-item list. Routing of the inf orsation and can become aware of internal information. f documentation of the review by appropriate station personnel rmt-s the l ORC meetings enable responsible person:al to responsibility of IRMG.
jointly assess recommended actions prior to and during implementation.
NOTE:
Refer to the Operating Experience Assessment Program Plow Cbsr .
Attachment A to this Procedure, f or guidance in the routing af information.
B. External Documents to be Reviewed
- 1. The OSS&PG will routinely receive and review the f ollowing external documents:
- a. LERs from sister pli.nts (Dresden 11. Monticello, M111stene 1) -
these documents may be prescreened by the INP0/NSAC sig:ificant event evaluation and information network.
- b. INP0/NSAC correspondence - this includes reports published by -
i
' these organizations. Significant Operating Events Reports (SOERs)
Significant Event Reports (SERs), Operating and Maintenance Reminders (0&MRs).
- c. Pertinent NRC or industry assessments of operating experiences including GI Service Information Letters (SILs) .
- d. Notepad
- e. NRC Circu~ars, Information Notices Bulletics - these documents vill be processed by the current methods employed by licensing.
C.
Methods Used for Determining Applicability and High Priority itfermation and Routing Ext e rnal '*
- 1. The OSS&PG will review the external documents listed above.
documents determined to contain operating inf ormation impc-tast to .,
plant saf ety will be assigned a POE1 number if the informative may be k applicable to PNPS 1. The POEI number will allow retrieval cf reviewed documents of importance. ':-
i
- 2. The following section criteria vill serve theasultimate a guideline inindetermining f actor determining applicability to Pilgrim Station, but ,
applicability is the good engineering judgement of the reviewer.
- a. Does the inf ormation apply to all plants?
- b. Is the information from a sister plant (Monticello, Nsden II.
Millstone I)?
- 1.3.33 4 Rer. .
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- c. Dogs,*t{e*}c.pcIagtbg gply t).e. ogyss ee,qrtsggpa d os sie p r,tb., e those at Pilgrim?
- d. Does the information contain procedural or operator errors which could occur at Pilgrim Station?
- 3. Informatica which is applicable to Pilgrim Station will then be screened for significance using the 1NP0/NSAC screening criteria (Attachment B to this procedure) as a guideline. If necessary, the reviewer should consult other technical personnel using existing work control system to make this decision. Events determined to be "Not Significant" will be dispositioned and closed out by the reviewer.
This may include routing of information to potentially interested individuals but the overriding objective is to assure that plant personnel do not routinely receive extraneous and unimportant infor-nation on operating experiences in such volume that it obscures priority information. ,, .
Items deter = h.d to ,be'" conditionally significant" will be dispositioned in the same ' as "significant" items unless downgraded to the "not significant category with the concurrence and approval of the 0.5.5.&P. Group Leader.
4 For applicable items, deemed to be significant, the reviewer will reconmend disposition and f orward to POEAC f or broader technical review and determination of appropriate recommended action, including priority. The recommended action can be one of the following:
- a. a recommendation to change plant procedures
- b. a recommendation to change or evaluate changing plant design I c. a recommendation to incorporate information into training and retraining programs.
- d. a recommendation to route as inf ormation to designated plant personnel.
- s. a recommendation to initiate a study (action item)
- f. a recommendation as to a course of action (Action Plan)
- g. no action required
- 5. If the document contains information which the screening individual feels may be of an urgent nature, the document will be submitted to the On-Site Safety and Performance Group Leadsr (OSS&PGL) uhe will determine appropriate dissemination of the information. With con-currence of the Training Manager and Station Manager, the OSS&PGL may elect to have the on-shif t STA provide training to operators on 3 J
information of suf ficient importance that it should not weit for enthasis through routine training and ' retraining programa. As a guideline. criteria f or determining urgency are as follows:
- a. A major deficiency in design, ecostruction or operation having safety implication requiring immediate remedial action.
- b. Series of events (where individual events are not of major importance), recurring incidents, and incidents with implications for similar facilities (generic incidents) which create major saf ety concerns.
- 6. Action Recuired. Inf ormation or Close-Out .
i i The POLAC will determine if applicable inf ormation determined to be s gr.ificant to PNPS 1 requires action, routing as information to appropriate PNPS 1 personnel or should be closed-out.
1.3.33-5 Rev. 1
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- 81. Two .a more f a11eres .erar _ C1. A e&ngle f ailure seters is ~~ 31. A stagne is11ere ecosts Le redundset eyesens dering e mem-redundant system. 1a a redundant erstem. i
- **** "**** e Does the fallare vie R2. neo-critical d.egradet.is>me I
- 82. Two . more f ailures ese t. ,ramary. see.noary. .tata r of.toundarse eest speaa. j e raammen cesse occur 4. ring sentatament pressure bened. Lag leaks. e41 leaks , -
the same e. cot. ary. . tee leans , ets. ) . ]
~~"" st. Three er more failures secur e Does the failure lead as a 33. Paramanet err.rs and pr derist the same event. me)er plant transient (e.g., ee h a3 estartencies are -
- 84. Campement f auern escur oweroseling, less of heat emummitted that e. not '
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that woulf b.we .estly escaped eetortiam by testing ressat f,g a,gg ag,,,g,,res ,*
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""" C2. Tw a, par.ently failsres unrelated com: Geraag the 54. Saimmar .efistemetes .ceur
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stymificamdy 44if areet irom o Ate the iallar.s sammes ****I*
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or than wesad be aspectedt e 1s the returfense rate Leeresslagt -
,,,,,,,, cf . Other leerple tal .
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FIGURE 1. NSAC Screening Sheet
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ATTACEMDrr B 1.3.33B-1 Rev. 1
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