IR 05000440/1988013
| ML20154P436 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/26/1988 |
| From: | Gardner R, Westberg R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20154P428 | List: |
| References | |
| 50-440-88-13, NUDOCS 8810030063 | |
| Download: ML20154P436 (6) | |
Text
_ _ _ _ _ _ _ _ _.
_ _ _ _ _
_ _ _ _ _ _ _.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ -
.
.
.
U. S. NUCLEAR REGULATORY COMMIS$10N
.
.
REGION !!!
Report No. 50-440/00013(DRS)
Docket No. 50-440 License No. NPF-58 Licensee:
Cleveland Electric Illuminating Ccepany 10 Center Road Perry. OH 44081 Facility Nerne: Perry Nuclear Power Plant. Unit 1 Inspection At:
Perry Site, Perry Ohio Inspection Conducted: August 30 to Septerber 1 and Septcrber 13-15, 1904
- Q'es tbergM2
,/u /sa Inspector:
R. A.
Cate j
hk.
dW f
f Approved By: Ronald N. Gardner, Chief 3, l. k N Plant Systems Section Date l
l Inspection Summary
,
Inspection on August 30 to September 1. and Septerter 13-15. 1988 (Report l
No. 50-440/88013[0R5))
i Areas Inspected: Licensee action en previously identified inspection findings (52701. 92702) and licensee compliarce with 10 CFR 50.62, the ATWS Rule, t
per TI 2500/20 (25020) $!PS No. A-A-20.
t I
l Results: Three previously identified inspection findings were closed.
The inspection required by T! 2500/20 was ccepleted; however, the review of the
,
design remains open pending issuance of the site specific SER. Based on the
!
inspection, the inspector reached the following conclusions:
The systen for retrieval of training records is excellent.
!
Licensed personnel in the control roorn appear to be well trained and i
knowledgeable in ATWS systems.
l QA SNS SNk$
-
. _
_ _ _ _ _ _ _ - _ _ _ _ _ _ _
l
.
?
.
i DETAILS f
.
.
b 1.
Persons Contacted i
Cleveland Electric Illuminating Company (CEI)
j i
R. V. Tanney, Engineer, IC&E G. G. Rhoads, Licensing Engineer G. A. Dunn Supervisor, Compliance i
A. G. Migas, Senior Project Engineer, !&C l
D. R. Green Manager, Electrical Design R. J. Tadych, Manager, Mechanical Design
T. A. Boss, Supervisor, Quality Audit
M. P. Lazar. Supervisor, Operator Training i
C. E. Persson, License Training Instructor l
- D. C. Jones Ops Engineer l
- R. A. Newkirk, Manager Licensing and Cunpliance t
- D. P. Igyarto, Manager Training
{
- R. A. Stratman, Ops Manager i
- C. H. Shuster, Director, NED
- L. E. Hartline Manager, PAQS l
- B. D. Walrath, Manager, EPSS
'
U. S. Auclear Regulatory Comission (USNRC)
G. F. O'Dwyer, Resident Inspector
- Indicates those attending the exit meeting on September 15, 1988.
Other personnel were contacted as a matter of routine during the
{
inspection, j
2.
Licensee Action on Previous Inspection Findings a.
(Closed) 440/87019-01A (Violation): The licensee failed to conduct an engineering review o" three outstanding repetitive tasks
+
(preventive maintenance). The inapector verified that repetitive
!
task Nos. R85003699, R66004208,.nd R8500145 were completed or
!
rescheduled as required.
The inspector reviewed the revision to
Procedure No ON1A: PAP-0903, "Repetitive Task Programs," Revision 3,
!
which provided for a periodic engineering review and disposition of i
outstanding repetitive tasks and Procedures No. CM1A: PAP-0906, i
"Control of Maintenance Section Preventive Maintenance," Revision 1, and No. OM1H:!AP-0501, "Calibration /Leop Calibration Check."
Revision 1, which added a Preventive Maintenance Evaluation /
Justification Sheet to the procedures. The inspector also reviewed Attachnent 3 to Desk Guide-!CS-006. "Technical Reviews.* Revision 0, which outlined repetitive task deferral review considerations and guideline No. PPTO: PEG-C00, "Plant Engineering Guidelines "
l Revision 0, which discussed repetitive task deferrals / rescheduling.
This item is considered closed.
I
f
-
-- - -- -
-
-- -
-
-
-J
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
____
.
l
.
'
I b.
(Closed) 440/87019-01B (Violation): The licensee failed to conduct
,
.
all lifted lead and jumper log reviews as required by the
!
l procedure. The inspector reviewed the repetitive task No. R86010411
'
suenary and LL&J/MFI tagout audit sheet which indicated that the i
required reviews were perfomed in April, June, and November of 1986
and May 1987.
This item is considered closed, j
c.
(Closed) 440/87019 02 (Unresolved item):
Potential problems
!
identified in work order (WO) write ups lack corrective action
!
documentation and resolutions.
The inspector verified that the
,
problems identified in Work Order Nos. 870C07285, 870007145, and 870007230 were corrected.
The inspector reviewed the revision to
Procedure No. OM1A: PAP 0905, "Work Order Process," Revision 7, which
.
added a "Work In Progress Description Log," to record problems r
.
encountered and to document followp actions.
The inspector also
'
reviewed CA Checklist No. D-0031. "Final Review of Conpleted Work
)
Order Packages," Revision 9, which required review of and
,
reconciliation of all cceents documented by the work group indicating l
l open or unresolved items.
This item is considered closed.
!
,
d.
(Closed) 440/87019-03 (Deviation): Separation deviations and other l
!
deficiencias were noted in RP5 panels.
The inspector toured the
-
!
control room and verified that the separation deviations and l
deficiencies in RPS panels Nos. H13-P691, P692, P693, and P694 had (
been corrected. This item is considered closed.
]
.
!
3.
Ten &orary Instruction (TI) 2500/20 (SIMS Number MPA-A 20) (Closed)
!
The purpose of this inspection was to determine whether Anticipated
!
Transient Without Scram ( ATWS) mitigating systems that are not (
safety-related comply with the 10 CFR 50.62 rule, to determine whether i
j the CA controls applied to rajor activities (design, procurement.
l
]
installation, and testing) for ATWS equipment that is not safety-related
i complied with Generic letter (GL) 85-06, and to assess the operational
j readiness of ATWS equipment that is not safety-related.
l
!
10 CFR 50.62, 'The ATWS Rule," requires three systems to nitigate the i
j consequences of an ATWS event.
They are Reactor Pump Trip (RPT),
i Alternate Rod Insertion (ARl), and Standby Liquid Control System (SLCS)
f j
i with a minimum flow capacity and boron content equivalent in centrol
!
capacity to E6 gallons per minute of 13 weight percent sodium pentaborate
solution.
!
"
Ferry Nuclear Power Plant (FNPP) installed the redundant reactivity
control system (RRCS) during the initial censtruction phase of the plant
,
J under an Appendix B Quality Assurance Program. At PNPP the RRCS consists
'
I of the AR!, RPT, and the required SLCS plus an additional feedwater i
l rentaek provision.
The ARI and RPT are Class IE electrical systems and the SLCS is a Category I seismic system. Since these systems are
,
i safety-related and were installed under Appendix B controls, they exceedsd l
the guidance given in Generic Letter 85-06. Therefore, this inspection j
l concentrated on the confimatien of completed work and personnel f
j qu611fications and training for ATWS systems only,
,
i
i I
'
.
-
--
.
.
-
-
-
=
>
_ _ _ _ _ _ _ _ _ _ _ _ _ _
.
.
.
a.
Docurrentation Reviewed
.
(1) letters (a) PY-CE!/NRR-0190L, M. R. Edelman to B. J. Youngbiood,
"Compliance with ATWS Rule." dated March 19, 19t$.
(b) PY-CE!/NRR-0375L, A. Kaplan to NRC, "Response to NRC P.equest for Additional Infonnation on Cornpliance With 10 CFR 50.62." dated July 12, 1988.
(c) PY-NRR/CEl-0410L, T. A. Colburn to A. Kaplan, "Standby Liquid Control System (SLCS) Testing to Ensure Cunp11ance With 10 CFR 50.62 for the Perry Nuclear Power Plant (PNPP)
Unit 1," dated August 15, 1988.
(2) Procedures (a) No. OM3A:50!-C22, "Redundant Reactivity Control System (Unit 1)," Revision 2.
(b) No.OM4B:0N!-C71-1,"Re:ctorScran(Unit 1)"Revision 0.
(c) No. OM4C:PEl-B13. "Reactor Pressure Vessel Control,"
Revision 1.
(d) No OM7A:SVI-B21-T0246-A, B." ATWS-RPT Logic System Functional Test for Division 1/2," Revision 1.
(e) No. OM7A: SUI-B21-T0210A, B, E. F "ATWS-RPT Reactor Yessel Water Level 2 Channel functional for 1821-N402A, B. E, F," Revision 2.
(f) No. 0M7A:SY!-B21-T0211A, B, E, F. "ATWS-RPT Reactor Water Level 2 Channel Calibration for 1821-N402A, B. E, F,"
Revision 2.
(g) No. OM7A:SY!-B21-T0212A, B E F. "ATWS-RPT Reactor Vessel Pressure High Channel Functional for 1821-N403A, C, E F,"
Revision 2.
(h) No OM7A:SVI-B21-T0213A, B E. F "ATVS RPT Reactor Vessel
'
Pressure High Channel Calibration for 1821 h403A, B. E F,"
Revision 2.
(i) No. OM7A:SY!-C41-T02001 "Standby Liquid Control Pump and Valve Operability Test " Revision 4.
'
(j) No. OM7A:SVI-C41 T2002, "Standby Liquid Control System i
Operability," Revisten 1.
,
)
__
_ ___
_
.,
(k) No. OM7A: gel-0116. "Maintenance of 12.CKY A.E. Power-Yac Vacuum Breakers," Revision 0.
(3) f,HPP Updated Safety Analysis Report (USAR)
(a) Section 4.6.1.1.2.5.4, * Alternate Rod Insertion (ARI)".
(b) Section 7.6.1.12. "Anticipated Transient Without Scram ( ATWS) Instrumentation and Controls".
(c) Section9.3.5,"Standby'.iquidControl(SLC) System".
(d) Appendix 150, "Anticipated Transients Without Scram (ATWS)".
(4) System Description Manual, Chapter C22. "Redundant Reactivity Control," Revision 4 (5) Drawings (a) No. D-206-065 Revision D.
(b) No. D-200-023 Series, "RRCS".
(6) Tra_ining Scenarios
(a) No. OT-3034-019-00, "Failure to Scram with ATUS".
(b) No. OT-3034-039-00, "Failure to Scram, Failure of ATWS, Challenge to Contaircent, and SLC".
(7) Course Completten and Training Records for Crews On Shift Relative to ATh$ Training, b.
Inspection Results The inspector verified the following aspects of the PNPP ATwi mitigating systems.
(1) The required ATWS mitigating systets were designed, installed, and tested in accordance with established procedures.
Perfomance to date has been satisfactory; however, the licensee's design has not been endorsed by c hRR safety evaluation (SE.'t). Pending the inspector's review of the forthcoming SER, this is considered an open iten (440/88013 01).
(2) Operating procedures have been written and implenented for the RRCS. A review of the training records for all reactor operators (R0s) and senior reactor operators (SR0s) currently on shift indicated that they had been trained en the procedures and operation of the systers.
_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _
____
_
_ _ _
_ - _.
.
...
(3) Surveillance procedures for ARI/RPT and SLC were implemented.
The inspector reviewed a sample of the procedures for one train
-
of the level and 5 essure surveillances with acceptable results.
(4) The inspector verified that the RRCS has been tested at power following installation. This is accomplished by only testing one train of logic at a time which maintains ATWS mitigation capability during the test.
(5) Permanent test switches were observed on each RRCS cabinet for testing logic. The system does not have bypass switches for maintenance and testing (optional).
(6) Review of the RRCS schematic control diagrams verified that once the ARI was initiated there was a 30 second time delay built in to ensure that the system would complete its action (all rods inserted). Once the system times out, return to normal operation is accomplished with reset switches.
(7) Manual initiation of the RRCS was verified by observance of the manual initiation switches on the H13-P680 panel benchboard of the control room.
(8, One R0 was interviewed relative to location of ATWS controls, indicators, and system operation. The R0 accompanied the inspector on a control room tour. One supervisor on shift was interviewed relative to Emergency Operating Procedures ATWS entry conditions, operator actions, and system operation. Both persons interviewed appeared knowledgeable and capable of operating the systems.
4.
Exit Interview (
The inspector met with licensee representatives denoted in Paragraph 1 l
during and at the conclusion of the inspection on September 15, 1988.
l The inspector sum 1arized the scope and results of the inspection and discussed the likely content of this inspection report.
The licensee I
acknowledged the information and did not indicate that any of the information disclosed during the inspection could be considered proprietary in nature.
-
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _