ML20196F452
| ML20196F452 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/25/1988 |
| From: | Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20150E198 | List: |
| References | |
| FOIA-88-198 NUDOCS 8812130087 | |
| Download: ML20196F452 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION UNITeo STATES y
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R MAY 251988 MEMORANDUM FOR: William T. Russell
\\f' Regional Administrator FROM:
Samuel J. Collins, Deputy Director i
Division of Reactor Projects
SUBJECT:
PILGRIM RESTART ASSESSMENT PANEL MEETING MINUTES p
On May 19,1933, the Pilgrim Restart Assessment Panel met via teleconference to discuss the status of NRC and licensee activities associated with the pro-posed plant Restart.
The following personnel were in attendance:
l i
Chairman:
Samuel J. Collins, Deputy Director, ORP Members:
A. Randy Blough, Chief, Reactor Projects Section No. 38, ORP Bruce A. Boger, Assistant Director for Region I Reactors, NRR Richard H. Wessman, Project Directorate I-3, Office of Nuclear Reactor Regulation (NRR)
Jacque D.
Curr, Chief. Engineering Branch, Division of l
Reactor Safety (ORS) j.
Ronald R.
Bellamy, Chief, Facilities Radiological Safety and Safeguards Branch, DRSS Others:
Daniel G. Mcdonald, Project Manager, NRR i
Lawrence T. Deerflein, Project Engineer, RPS 3B, ORP Clay C. Warren, Senior Resident Inspector, Pilgrim l
l Jeffrey J. Lyash, Resident Inspector, Pilgrim l
Tae K. Kim, Resident inspector, Pilgrim i
Frank M. Akstulewicz, Senior Technical Advisor, PTSB, NRR f
The panel discussed the issues from the last meeting, as well as the overall I
i integration of NRC inspection and review activities. As a result of the meet-l ing, the belcw listed actions with responsibility were agreed upon by the i
Panel.
l A panel meeting will be held onsite, June 1,1988, at 1:00 p.m.
(Bridge No.
492-9894).
All items below will be updated.
No separate agenda will be provided for the June 1 meeting.
Task Responsibility Oue Date 1.
Plant Status Update Resident Inspector Next Panel I
2.
Staffing / Organization Update Resident Inspector Next Panel l
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$$$21E8?g7 eacoa JOHNSON 88-190 PDR i
Memorandum for William T. Russell 2
MAY 251988 Task Responsibility Due Date 3.
Site Inspection Activities Resident Inspector Next Panel Update 4.
NRR to ask BECo Licensing the Mcdonald N4xt Panel status of once per cycle (OOC) surveillances 5.
Update concerns with MSTP Warren Next Panel 6.
Review and update NRC Restart All Next Panel checklist, identify items (either currently open or closed) for recheck during IATI 7.
Provide OIL Updates All Next Panel 8.
Restart Assessment Report Ocerflein Next Panel Format Update responsibility Blough Next Panel assignments for all sections 9.
Independent Assessment Team Deerflein Next Panel Inspection Plan
- 10. Update IATI Organi:ation Blough Next Panel Chart / Team Members
- 11. Update Overall Milestone Collins Next Panel Schedule
- 12. E0P Open Item Status NRR/ ORS Next Panel
- 13. Update Subset Milestone All Next Panel Schedules
- 14. Update Status of Power Durr/Blough Next Panel Ascension Program Deficiencies
- 15. Update status of concurrence Wessman Next Panel and issuance of Commonwealth 2.206 Petition response 16.
SEP !ssues Status Boger Next Panel
t Memorandum for William T. Russell 3
gy & $ jggg Task Responsibility Due Date a
- 17. Approach to 6/9 Commissioner Mcdonald Next Panel Briefing (5/26 2:00 p.m.
pre-brief) l
- 18. Approach to ACR$ Metting Mcdonald Next Panel
/
'h Samuel J. Colli
, Deputy Director Division of Reactor Projects l
I
Enclosures:
1 1.
Pilgrim Overall Milestone Schedule. Revision 4
(
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2.
Pilgrim Subset Milestone Topic Listing, Revision 4 l
cc w/encis:
T. Murley, NRR F. Miraglia, NRR 1
]
T. Martin, NRR j
R. Wessman, NRR
- 0. Mcdonald, NRR I
5 j
F. Akstulewicz, NRR
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i J. Roe, NRR l
J. Hannon, NRR i
W. Regan NRR 1
B J. Allan, RI W. Kane, RI J. Wiggins, R!
R. Blough, RI G. Sjoblem, R!
J. Ourr, RI j
R. Bellamy, RI L. Doerflein, RI M. Kohl, RI I
C. Warren, SRI - Pilgrim i
j J. Lyash, RI - Pilgrim T. Kim, RI - Pilgria s
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CAL 86-10 IM D m SIONR M M STON Q SALP Diagnos.
CAL 86 RFO-7 l#
Tea:n 10 AIT Restart SALP 85-99 Start Meeting Assess from Plan 85-99 Insp.
Plt Ser
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Assess 86-41 Plan BECo Rev. O g
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7-10/1/84-2/16/86-4/12/86 7/86 8/27/86 11/24/86 11/1/85-7/8/c7 7/8/87 7/30/87 10/31/85 3/7/86 1/31/87 BECo Nuc T&"
! 5EP Ltr' EP Ltr '
BECo tsRR Mtg' PWR Asc Restart l Site R'#1i "-
LOOP 9
Self to to EP with Prg Plan Work ent All Int Rev BECo 8ECo
Response
BECo Subnit Rev. 1 Stop E
E K
K E
A K
E E
E 8/5/87 8/21/87 9/17/87 9/17/87 9/24/87 10/15/87 10/26/87 11/8/87 11/12/87 12/87, Public Mtg Start BEC7 BECo SEP FiRC All Re-BECo/NRC NRC Public BECo Self on Restart Pre-Self Ltr to NRC start Plan Resolution Mtg Re:
Assessment Restart Pilgric:
INPO Plan Task Plan Assessment Except DTV Coments to R/S Plan R% tart Plar Report i
m App 7 Force BECo Comer."
.oments Complete 5
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5 I/4/88 1/27/88 2/18/88 2/22/83 2/22/88 3/18/88 5/6/88 5/11/88 5/9-20/83 15/26/88l NRC Rev of BECo Self-BECo Decis-S*"I""
1ATI Cocinission NRC Resolu-of BECo Assess /INPO ion on and Management Self-Assess Rpt Results repara-Briefing III0 -
IATI tion of SEP lisit Ltrs Re: IAT I IATI 0"5 Report Issues ment Rpt Presentatloa Readiness Issue I
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NRC Comp NRC 2.206 NRC Restart Restart 3
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Restr-t Power IATI Public Assess.ent Assessment dd 2.206 bk SRP EP Issue Ascension Public Meeting Report Panel Recon I55"'
Status Plan Rev
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ENCLOSURE 2 Subset Milestenes Topic Listing Area Responsibility A.
Overall Milestones 5 Collins B.
Pubite and State Involvement R. Blough Meetings with Licensee C.
NRR Actions for Restart D. Mcdonald D.
Management Transition C. Warren E.
Site Inspections / Reviews R. Blough F.
Assessment Panel Activities S. Collins G.
SALP C. Warren H.
EP Status R. Bellamy Restart Assessment Report (RAR)
L. Doerflein J.
Integrated Assessment Team Inspection (IATI) R. Blough K.
Power Ascension Program J. Durr S. Collins Ptigrim Subset Milestones 5/25/88 Rev. 4
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 5
OFFICE OF GOVERNMENTAL AND PUBLIC AFFAIRS, REGION I k**..*
475 Allendale Road, King of Prussla, Pa.19406 Tel. 215 337 5330 No I-88-80
. June 1, 1988 tontact:
Karl Abraham NOTE TO EDITORS AND STATION ASSIGNMENT EDITORS y
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A. Randy Blough, Chief of the Reactor Projects Section that inspects Pilgrim has issued a status report summarizing activities of the inspection staff during the per Ld May 7 - 20, 1988.
The report is attached.
NNN May 25, 1988 Docket No. 50-293 MEMORANDUM FOR: James T. Wi gins, Chief Reactor Pro ects Branch No. 3 FROM:
A. Randy Blough, Chief Reactor Projects Section No. 3B
SUBJECT:
PILGRIH STATUS REPORT FOR THE PERIOD MAY 7-20, 109a Enclosed is the Pilgrim bi-weekly status report from the NRC U <..t Office at Pilgrim.
Three resident inspectors monitored act.ivities at the plant during the report period.
In addition, two fire protection specialists from NRC Head-quarters were onsite to review selected fire protection program issues.
On May 11, 1988, NRC conducted a public meeting at th'e Plymouth Memorial Hall in Plymouth, Massachusetts to discuss the evaluation of public coments and concerns expressed during the February 18, 1988 public meeting on the Boston Edison Company's Pilgrim Restart Plan.
The status reports are intended to provide NRC management and the public with an overview of plant activities and NRC inspection activities.
Subsequent inspection reports will address many of these topics in more de+. ail.
(Original Signed by)
A. Randy Blough, Chief Reactor Projects Section No. 3B
Enclosure:
As stated (more)
, blind 2 2 0FFICIAL RECORD COPY PA0 I-88 0001.0.0 05/31/88 nmwnw
2 ENCLOSURE PILGRIM STATUS REPORT FOR THE PERIOD MAY 7 - 20. 1988 1.0 Plant Status As of 8:00 a.m. on May 20,1988, the reactor was in cold shutdown mode with moderator tamperature about 93 degrees Fahrenheit.
2.0 Facility Operations Sumary The plant has been shutdown for maintenance and to make program improve-ments since April 12, 1986.
The rector core was completely def ueled on February 13, 1987 to facilitate extensive maintenance and modifit.nion of plant equipment.
The licensee completed fuel reload on October 14, 1987.
Reinstallation of the reactor vessel internal components and the vessel head was followed by completion of the reactor vessel hydrostatic test.
The primary containment integrated leak rate test was completed during the week of December 21, 1987.
3.0 Items of Special Interest NRC Public Meeting to Discuss Coments on 8Eco's Pilorim Restart Plan on May 11, 1988, NRC conducted a public meeting in Plymouth, Massachusetts to discuss the evaluation of public coments and concerns expressed during
- the February 18, 1988 public meeting on the Boston Edison Company's Ptigrim Restart Plan.
The meeting took place in the town's Memorial Hall f rom 7:00 p.m.
to 11: 30 p.m.
Because the coments from the February 18 meeting covered a very broad spectrum of issues, the panel of NRC presented several discussions.
Each was designed to be management generally informative regarding NRC processes and to respond to the broad Also, a handout describing range of coments in a given subject area.
NRC s responses was distributed at the meeting. A forum was provided for state and local elected officials and private citizens to coment and ask questions on NRC's responses.
The NRC panel consisted of Mr. Samuel J. Collins, Deputy Director, Division of Reactor Projects, NRC-Region I; Dr. Ronald R. Bellamy, Chief. Emergency Preparedness and Radiological Protection
- Branch, NRC-Region I;
Mr. Jay M. Gutierrez, Regional Counsel, NRC-Region I; and Mr. Bruce Boger, Assistant Director for Region I Reactors, NRC-NRR.
The transcription of the meeting will be made available to the public.
(more)
. blind 2 2 0FFICIAL RECORD COPY PA0 1-88 80 - 0003.0.0
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Institute of Nuclear Power Coerations $lte Visit The Institute of Nuclear Power Operations (INP0) is an organization com-l posed of, and supported by, electric utilities who own and operate nuclear power plants.
INP0 assists utilities in improving programs and perform-ar.ce at their nuclear facilities.
A twenty-one member INPO evaluation team was onsite at Pilgrim on May 9-20, 1588, for a two-week inspection i
visit. Team members evaluated the areas of plant operations, maintenance l
chemistry, training and qualifications, radiation protection, industrial 7
safety, technical support, and organization and t.dministration.
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Licensee's $ elf Assessment The licensee completed a formal management self assessment of their readt-ness for restart.
The licensee has comitted to provide a report of the assessment results to the NRC.
NRC will review the results of the l
licensee's assessment prior to conducting a comprehensive NRC Integrated i
Assessment Team Inspection.
i NRC Assessment Panel Meetino On May 12,1988, members of NRC management from Region I and NRR met at t
the licensee's Chiltonville Training Center and discussed inspection plans with the NRC resident staff. The NRC Assessment Panel meets period-ically to coMNte the planning snd execution of NRC inspection and licensing activities related to Pilgrim.
The panel is chaired by Mr. $amuel J. Collins, Deputy Director, Division of Reactor Projects, NRC l
Region I.
}
4.0 Emergency Notification System (ENS) Report f
f Ouring this period, the licensee made the following report to the NRC l
pursuant to 10 CFR 50.72:
r On May 17, 1988, at about 11:30 a.m., the licensee inadvertently initiated the "A"
train of standby gas treatment and secondary j
containment isolation systems.
Licensee maintenance technicians were i
prepering to replace three primary contsineent isolation system logic l
relay coils.
As part of the equipment isolation, a logic power supply fuse was removed.
The licensee failed to fully identify the effect of deenergizing this portion of the logic.
When the fuse was removed the actuations occurred.
The fuse was reinserted and the isolation logic was reset a short time later, NRC review of this event will be documented in Inspection Report No.
50-293/88-19.
(mere)
. blind 2 2 0FFICIAL RECORD COPY PA0 1-88 80 - 0005.0.0
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5.0 NRC Staff Status Durina the Period j
The inspection staff at Pilgria during the report period consisted of the following:
Senior Resident Inspector
[
Clay Warren
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Resident Inspector Jeffrey Lyash Resident Inspector Tae Kim In addition, two fire protection specialists from NRC headquarters were onsite during the week of May 16, 1988, to review the licensee's enrrective actions on previous inspection findings.
The results of this inspection will be included in routine NRC Resident Inspection Report No.
50-293/88 19.
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UNITED STATES ~
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NUCLEAR REGULATORY COMMISSION 5
0FFICE OF GOVERNMENTAL AND PUBLIC AFFAIRS, REGION I 475 Allendale Road, King of Prussia, Pa.19406
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Tel. 215 337 5330 m
No. 1-88-88 June 16, 1988 j
Contact:
Kar.
.n NOTE TO EDITORS AG STATION ASSIGNMENT EDITORS A. Ra dy Blough, Chief of the Reactor Project: Section that inspects Pilgrim has issued a status report summarizing activities of the inspec',fon staff during the period May 21 to June 3, 1988.
Tri report is attached.
June 10, 1988 Occket No. 50-293 MEM0RANDUM FOR:
James T. Wiggins, Chief Reactor Projects Branch No. 3 FR:'4:
A. Randy Blough, Chief Reactor Projects Section No. 3B
SUBJECT:
PILGRIM STATUS REPORT FOR THE PERIOD MAY 21 - JUNE 3,1988 1
Enclosed is the Pilgrim bi-Hekly status report from the NRC 3esident Office at Pilgrim.
T'.ree resident inspectors monitored activities at the plant during the report period.
In addition, four regica-based specialist inspectors were onsite to review the licensee's radiation protection program ef fectiveness and i
the licenser s corrective actions on previous inspection findings.
On June 2,1988, Mr. James M. Taylor, NRC Deputy Executive Director for Regional Operations, and Mr. William T. Russell, Regional Administrator, Region I were onsite and toured the station, The status reports are intended te prcvide NRC management and '.he public with j
overview of plant attivities and NRC inspection activities.
Subs eqi.ent aninspection reports will address many of then topics in niore detail.
(original signed by)
A. Randy Blough, Chief Reactor Projects Section Nr 3B
Enclosure:
As stated (more) 17a.+
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ENCLOSURE PILGRIM STATUS REPO'lT FOR THE PERIOD MAY 21 - JUNE 3,1988 1.0 Plant Status As of 8:00 a.m. on June 3,1988, the reactor was in cold shutdown mode with moderator temperature about 95 degrees Fahrenheit.
2.0 Facility Operations Summary The plant has been shutdown for maintenance and to make program improve-ments since April 12, 1986.
The reactor core was completely defueled on February 13, 1987 to facilitate extensive maintenance and modification of plant equipment.
The licensee completed fuel reload on October 14, 1987.
Reinstallation of the reactor vessel internal components and the vessel head was followed by completion of the reactor vessel hydrostatic test.
The primary containment integrated leak rate test was also completed dur-ing the week of Oecember 21, 1937.
During this period, the licensee per-formed routine maintenance and surveillance tests including the local leak rate testing of selected containment isolation valves.
3.0 Items of Special_I_rterest Maintenance Work Restricted by Licensee Management On May 27,1988, Boston Edison management restricted performance of some mainte.1ance tasks at Pilgrim.
A licensee self-assessment completed on May 26 identified maintenance program weaknesses.
Several concerns regarding the effectiveness of the licensee's program for control of routine and corrective raintenance were also raised by the NRC during a l
I recent maintenance team inspection completed on May 5, as documented in a l
report issued May 25.
In addition, the licensee's Quality Assurance department recently identified similar concerns in the area of maintenance i
on environme m lly qualified equipment.
',censee management concluded and is station maintenance program are warranted, ions that changec the to address the problems.
The restrict on developing e
ons May 27, 1988 involved those maintenance tasks which were not covered by jo.b-specific, detailed, approved station procedures.
These jobs were restricted pending an additional management review.
Activities such as surveP lance testing and maintenance activities that are clearly delineated by detailed procedures were allowed to continue.
These rtstricted maintenance tasks were to be reviewed on a case-by-case basis and then released to the field if either 1) appropriate job-soecific procedures or instructions were written and applied, or 2) the additional review confirmed that existing controls were conservative for that job. All work released is being reviewed and approved by the Maintenance Section i
Manager.
The NRC staff considers the additional review to be a prudent l
measure.
(more) l i
2 Licensee's Submittal of the Self-Assessment Report l
t On May 26,1988, the licensee submittea to the NRC the Pilgrim Nuclear Puwer Station Self Assessment of Readiness for Restart Report and Volume 2, Revision 2 of the Restart Plan.
The licensee committed to pro-vide schedules for actions to address matters which were identified as restart issues in the self-assessment report.
This information, as well as the licensee's statement regarding readiness for a comprehensive NRC Integrated Assessment Team Inspection (IATI), is expected in a few weeks.
NRC staff review of the self-assessment report and additional submittals by the licensee will be completed prior to conducting a IATI.
Licege's Limited Stop Werk Order On May 19, 1988 the licensee's Quality Assurance Department issued a stop work order on certain maintena. ice activities involving Environmentally l
Qualified (EQ) equipment.
The NRC equipment environmental qualification regulations require that safety-related electrical equipment be designed and maintained to withstand the effects of an accident, such as high temperatures, humidity, and pressures.
The licensee's internal Quality i
Assurance audits identified several potential deficiencies in EQ mainten-ance practices.
The licensee has been evaluating the items and devcloping corrective actions whien include stringent control of maintenance on EQ equipment and training the maintenance personnel on the full requirements i
of the EQ program.
Although NRC was not involved in the initial stopping of work, the details of this item will be reviewed and documented in the res' dent inspection report 50-293/83-19.
Recent NRC Inspection Resul,1s, On thy 31,1988, HRC Region I issued the inspection report 50-293/88-12 documenting the results of a routine inspection conducted on March 6 -
April 17, 1988 by the resident inspectors.
Prompt and positive approach to problem investigation and root cause analysis was considered as a licensee strength.
The report identified a case of inadequate design l
control and review as evidenced by the incorrect installation of two reactor water level gauges.
Also, weaknesses in test procedures and technical reviews were identifieo in the pre-operational tests performed on these instruments.
The licensee is required to respond in writing within thirty days.
Inspection report 50-29;/88-13 was issued on May 26, 1988 documenting the results of a routine inspection conducted on April 11-15,1988 by two region-based specialist inspectors.
Areas inspected included followup on previous inspection findings in the area of material / component integrity and plant modifications and test procedures The inspectors reviewed eight previous inspection findings and
..iermined that they were tatisfactorily addressed by the licensee.
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On June 1,1988, NRC Region I issueJ inspection report 50-293/88-14 docu-menting the results of a routine inspection conducted on April 18-22, 1988 by a region based specialist inspector.
Areas inspected included the licensee's Power Ascension Test Program and previous inspection findings.
The Power Ascension Test Program was fcund to be acceptable pending com-pletion of unresolved items and additional review by the NRC staff.
Of l
four previous inspection findings reviewed, three are now resolved and one remains open.
Inspection report 50-293/88-16 was issued on May 24, 1988 documenting the results of a routine safeguards inspection conducted on April 11-14, 1988 by three region-based specialist inspectors.
Areas inspected included the licensee's program to upgrade physical security barriers, alarm stations, i
safaguards centingency plan implementation, and previous inspection find-ings.
The inspectors determined that the progress on security program upgrades is being made.
Seven previous inspection findings were reviewed and it was found that four items were satisfactorily addressed by the licensee.
Three previous violations on degraded vital area barriers were reviewed and the licensee's actions to prevent recurrence were found ade-quate.
These violations remain open pendino an NRC deteraination regardirg enforcement.
On May 25,1988, NRC Region I issued inspection report 50-293/88-17 docu-menting the results of a special maintenance assessment team inspection conducted on April 25 - May 5,1988 by five Region I staff.
The purpose of the inspection was to perform an in-depth assessment of maintenance program and management control.
No violations of the regulatory require-ments were identified.
However, significant maintenance prugram defici-encies were identified which should t,e addressed by the licensee prior to the plant restart.
The licensee was requested to respond in writing j
within thirty days identifying actions taken or planned to address these deficiencies.
NRC Assessment Panel Meetina On June 1,1988, members of NRC management from Region I met onsite and discussed inspection plans with tha NRC resident staff.
Members of the Office of Nuclear Reactor Regulation participated via teleconference.
The NRC Assessment Panel meets periodically to coordinate the plannin and execution of HRC inspection and licensing activities related to Pil rim.
The Panel is chaired by Mr. Samuel J. Collins, Deputy Director, Div sion of Reactor Projects, NRC Region I.
(more)
4 1
Scheduled NRC Commission Briefing On June 9,1988, a publicly held Commission meeting is schec'uled at the NRC offices in Rockville, Maryland to brief the Commissioners on the progress of the Pilgrim restart activities.
Representatives of the Boston Edison Company and the NRC staff will independently present the status briefings before the Commission.
4.0 Emergency Notification System (ENS) Report During this period, the licensee made the following report to the NRC pursuant to 10 CFR 50.72:
On June 2,1988, the licensee discovered during a routine quarterly sur-veillance test that both accumulators for the SLCS were low on pressure.
There is one accumulator on the discharge piping of each pump which dampens the pulsations from the pump.
Each is a steel vessel with a synthetic bladder.
The bladder's upper side is charged with nitrogen to about 500 Nig.
Both accumulators were found with less than 300 psig of nitrogen pressure.
The licensee determined tnat the system was inoperable based on a previous licensee engineering analysis.
Peak to peak pressure fluctuations of approximately 30-40% of discharge pressure can occur with.
zero accumulator pressure.
For an accumulator pressure of 300 psig the pressure fluctuations are reduced to 15-20% of the discharge pressure and at 500 psig the fluctuations would be approximately 5%.
On June 3, 1988 at 2:10 p.m., the licensee notified the NRC via the ENS of the inoperable SLCS.
Several attempts by the licensee to recharge the accumulators were unsuccessful.
The detsils of this item will be documented in the resident inspection report 50-293/88-19.
l The Standby Liquid Control System (SLCS) is a backup method for establish-ing and maintaining the reactor subscritical independent of control rods.
5.0 NRC Staf,f_ Status Ouring the Period The inspection staff at Pilgrim during the report period consisted of the followinc:
Senior Resident Inspector Clay Warren Resident Inspector Jeffrey Lyash Resident Inspector Tae Kim (more)
5 region-based spe:ialist inspectors were onsite to review the Four licensee s radiation protection program effectiveness and the licensee's corrective actions on previous inspection findings.
In addition, a resident inspector from the Susquehanna facility was onsite during the week of May 23, 1988 to assist the resident inspectors.
The results of these inspection activities will be documented in the NRC inspection reports 80-293/88-19, 50-293/88-22 rind 50-293/68-24, respectively.
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