IR 05000272/1989081
| ML18094B212 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek, 05000000 |
| Issue date: | 12/07/1989 |
| From: | Amato C, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18094B211 | List: |
| References | |
| 50-272-89-81, 50-311-89-81, 50-354-89-81, NUDOCS 8912270283 | |
| Download: ML18094B212 (8) | |
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Report No Docket N so.,.336 50-354 License N DPR-70 DPR-75 NPF-50 U.S. NUtLEAR REGULATORY
REGION I
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Licensee:
Public Servi~e Electric and Gas P.O. Box 236
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Rancocks Bridge, New Jersey 08038-4800*
Category C Category. C Category,C Facility Name: Artificial Island (Hope Creek and Salem Generating Stations)
Inspection_At: Lower Alloways Creek Township, New Jersey Dates:
October 24 to 26, 1989 Insp.ectors: c:-~.~t~~~am Leader, Emergency Preparedness Section, Region I Approved by.:
E. Fox, Senior Emergency Preparedness Specialist, Region I C. Gordon, Emerg~ncy Preparedness Specialist, Region I J. Jamison, Pacific Northwest Laboratories S. Pin ale, Salem Resident Inspector
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1 e, mergency rep are ness Sec on,
_ lity Radiological Safety and Safeguards Branch, Division of Reactor Safety and Safeguards ection Areas Inspected:
Routine, announced, emergency preparedness inspection of the licensee's annual, partial-participation,emergency exercise conducted on October 24 to 26, 198 The inspection was performed by a team of five NRC Region I and contractor personnel.
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Results:
No exercise weaknesses were identified. Public Service's emergency response actions were adequate to provide protective measures for the health and safety of the publi In addition, the habitability of the Salem Technical Support Center was reviewed and determined to be acceptable.
. 8912270283 891207
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DETAILS 1.0 Persons Contacted The following Public Service El~ctric and Gas personnel attended the exit meeting on October 26,1989. * *
R. T.. * Buricelli, General Manager, Information Systems and External Affairs LaBruna, Vice President, Nuclear Operations Crimmins, Vice President, Nuclear Engineering Connor, General Manager, Nuclear Services Di Guiseppi, Emergency Preparedne~s Manager Miller, General Manager, Salem Operations
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Miltenberger; Vice President and Chief Nuclear Officer Reiter, Manager, Nuclear Engineering Projects Salamon, Manager, Nuclear Public Information
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The inspectors also observed the actions of, and interviewed. other licensee personne.0 Emergency Exercise
- The Artificial Island announced, partial~participation exercise was conducted on October 24, 1989, 9:00 a.m. to 1:40 The States of Delaware and New Jersey ahd. two New Jersey Counties participate.1 Pre-exercise Activities The exercise objectives submitted to NRC Region I on June 21, 1989 were reviewed and, following revision, determined to be adequate to test the licensee's Emergency Pla On August 24, 1989, the licensee submitted the complete scenario package for NRC review and -
evaluation. Region I representatives had telephone conversations
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with the licensee's emergency preparedness staff to discuss the scope and content of the scenari As a result, minor revisions were made to the scenario which allowed adequate testing of the major portions of the Artificial Island Emergency Plan and Procedures and also provided the opportunity for the licensee to demonstrate those areas previously identified by the NRC as in need of corrective actio NRC observers attended a licensee briefing on October 24,198 Changes to the scenario made by the licensee were discussed during the briefing. The licensee stated that certain emergency response activities would be simulated and that
controllers would intercede in exercise activities to prevent disruption of normal plant activitie., Exercise Scenario The exercise scenario included the major following events:* Primary cool ant system 1 eak rate greater than make-up capacity; Small break loss of coolant accident inside tontainment; Interfacing system loss of coolant accident resulting in release of primary coolant system water into the auxiliary building;
-.Core uncovery an9 fue 1 over heating;
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Fuel damage and release of a portion of the fission product gap fraction activity;
- _Release of radioactive fission products* to the environment;
. and,. Restoration of core cooling, core recovery and termination of the environmental releas.3 Activities Observed During the conduct of the licensee's exercise, NRC team members made detailed observations of the activation and augmentJtion of the Emergency Response Facilities (ERFs).and the Emergency Response Organization (ERO) staff and actions of ERO ~taff during operation of the ERF The following activities were observed:
1. Detection, classification, and assessment of scenario events; Augmentation of the emergency organization and response facility activation;
- Direction and coordination of emergency response; Notification of licensee personnel and off-site agencies of pertinent plant status information;
_ Communications/information flow, and record keeping; Assessment of plant*conditions; 7. Assessment and projection of off-site radiological dose and consideration of protective' actions; and, Engineering analy~is of accident mitigation technique.0
Classificition of Exercise Findings Emergency Preparedness exercise findings are classified as follow Exercise Strengths
- Exercise strengths are areas of the licensee's response that provide *.
strong positive indication of their ability to cope with abnormal plant conditions and implement the Emergency Pla Exercise Weaknesses Exercise weaknesses are areas of the licensee's response in which th~
performance was such that it c6uld have precluded effective implementation of the Emergency Plan in the.event of an actual emergency in the area being observe Exist~nce of an exercise weakness does not of itself indicate that overall response was inadequate to protect the health and safety of the publi *
Areas for Improvement An area for improvement is an area which did not have a ~ignificant negative.impact on the ability to implement the Emergency Plan and response was adequat However, it should be evaluated by the licens~e to dete'rmine if corrective action could improve performanc.0 Exercise Observations
_The inspectors observed licensee response actions in the emergency response facilitie Control Room The following exercise strengths were identifie.
The operators effectively implemented Emergency Operating Procedures throughout the exercis.
- 2. *There was very good communication among the operator.
Timely and succinct staff briefings were hel.
Accident classification was rapid and correc.
Operators were.proactiv No exercise weaknesses were identifie The following area for improve~ent was identifie Thers was a 39 minute delay in announcing to the control room staff the dec.l arat ion of a General Emergenc.
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Technical Support Center (TSt)
The following exercise st~engths Were identifie.
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TSC staff briefings and manager's conferences were freq~ent, thorough, and used effectively to assign prioritie The Emergency Duty Officer (EDD) in charge of the TSC maintained.an accurate and ongoing awarene~s of plant status relative to Emergency Action Level classificatio *
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The EDD wa~ proactive and directed the TSC staff to anticipate change.
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.There was timely and accurate assessment of core cooling status~
The TSC Technical Support Mana~er assigned action items to the Emergency Operations Facility ln the areas of logi~tics and engineering suppor On site radiolag1cal measurements were correlated with projected dose value *
No exercise weaknesses were identifie The following areas for imprbvement were identifie The EDO~did not direct the TSC staff to develop a back-up method to *
maintain restored core cooling (for example, refilling the Refueling Water Storage Tank).
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- The TSC Radiation Protection staff did not correlate Radiation Monitoring System readings with containment status for 40 minutes following restoration of containment isolatio.
The EDD did not within a reasonable time advise the Control Room he had assumed the EDD functio Operational Support Center (DSC)
The following exercise strengths were identifie.
The DSC Coordinator gave good staff briefings and effectively used the DSC staf *
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The OSC Coordinator maintained good command and control through-out the exerC:i s There was ~ood toordination with the Health Physics Control Poin Response of personnel during the medical drill was prompt and correc There were very good briefings of in-plant team Assignments were clearly given, allowable personnel doses noted, and communication with the teams when in-plant was maintaine.
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No weaknesses were identifie The following areas for improvement were identifie Forty minutes were needed to complete accountability. Procedures and practices were not consistent. A manual method is in use to check personnel leaving the protected are * Two small, shielded transfer casks are available for Post Accident Sample movemen Selection of the cask to be used_ is based on a survey of the sampl This procedure should be reviewed to determine if ~single cask can be use Emergency.Operations Facility (EOF)
The fo 11 owing exe_rc i se strengths were i dent i fi e There was excellent command and control and frequent, detailed staff briefings by the Emergency Response Manger (ERM). The ERM held frequent, interactive staff meetings which included State representatives at the EO * There was very good interadion with and support of the.Delaware and New Jersey representatives at the EO. There was a very detailed discussion of Protective Action Recommendation * The ERM promptly recogniied containment failure and correctly c1assified it as an interfacing system loss of coolant acciden.
Excellent radio communication was maintained with the off-site, radiological monitoring teams including the airborne.tea Teams were regularly updated as to plant status, classification, PARs and meteorological condition _ *. Good and on-going communication was maintained with the Technical Support Center and the Emergency News Cente * All prissible bases for event classification were reviewed.*
. No exercise weaknesses were identified.*
Emergency News Center The following stren~ths were identifie Changing plant conditions were pr.omptly reporte.
Effective use was made of visual ~ids when ~iscussing plant conditions. -
No weaknesses were identifie No areas for improvement were identifie.0 Licensee Action on Previously Identified Items Th_e following items were identified during the previous exercis Based upon observation made by the NRC team during this exercise, review of the scenario, and information provided by the controllers, the following item was not repeated and is close :
(CLOSED) (50-272/88-23.:.01 and 50-311/88-26-01) IFI The licensee's staff failed to recognize containment failure.* Containment failure was promptly recognized and the failure mode correctly identifie f CLOSED) (50-272/88-23-02, 50-311/88-26-02 and 50-354/88-26-01) IFI The icensee's Emergency Operations Facility (EOF) staff did not recognize core stability and recovery conditions. The EOF staff identified core.
stability and recovery conditions in a timely manne *
5.0 Licensee Critique The NRC team attended the licensee's exercise critique on Octobe~ 25, 1989 during which the licensee's lead controllers discussed observations of the exercise. The licensee's critique was critical and thoroug The licensee indicated that these obsetvations would be evaluat~d and appropriate corrective actions take.0 Salem Technical Support Center (TSC)
The Salem Station has operated with an interim TSC in keeping with a license condition (refer to Section 9 of NRC RI *combined Inspection Report Nos. 50-272/89-05, 50-311/89-05 and 50-354/89-05).
The interim TSC did not meet the habitability ~equirements of Section 8.2.1.f of Supplement I to NUREG-073 The licensee conducted a self assessment of the TSC in order to identify areas for corrective action and improvemen Based on the results of this review, a program was implemented to upgrade the Salem TS This program was completed at the time of this inspectio The Inspectors observed -a power interruption test and reviewed
- documentation which demonstrates by calculation that the upgraded Sale TSC meets habitability r~quir~ment *
Based on the above, habitability and back-up power requirements are met for the Sal em TSC.. *
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7.0 Changes to the Em~rgency Preparedness Program (EPP) Management Staff An EPP staff member has been selected to succeed the former EPP Manage This individual has been employed by Public Service for almost ten years..
About half of this time has been spent with the EPP.. He was formerly the EPP Administrator for Nuclear Off-Site Emergency Preparednes The
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inspector had no further questions in his are *
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8. 0 Exit Meeting *
Followiri9 the licensee's self critique, the NRC team met with the licensees representatives listed in Section 1 to discuss findings as detailed in this repor *
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The* NRC team i eader* summarized the observat i oris made during the exercis The licensee was advised no exercise weaknesses were identifie Although areas>for improvement were identified, the NRC team determined that within the scope and limitations of the scenario, the licen~ee's performance demonstrated they.could implement their Emergency Plan and Emergency Plan Implementing Procedures in a manner that would adequateJy provide protective measures for the health and safety of the publi During a second Exit Meeting on October 27,1989 attended by Emergency Program (EP) management and the General Manager to whom the EP manager reports, the inspector discussed the Salem TSC and EP management staff change The licensee was advised no violations were identified.