IR 05000244/1979002
| ML17244A422 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/16/1979 |
| From: | Dante Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17244A421 | List: |
| References | |
| 50-244-79-02, 50-244-79-2, NUDOCS 7904020028 | |
| Download: ML17244A422 (16) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION-AND ENFORCEMENT Region I Report No.
5O-244/79-O2 Docket No.
5O-244 License No.
Priority Rochester Gas and Electr ic Corporation 89 East Avenue Rochester, New York 14649 Category C
Fac i 1 ity Name R.
E.
Ginna. Nucl ear Power Pl ant, Unit
nspection at:
Ontario, New York Inspection conducted:
Ja uary 29-31, 1979 Inspectors:
o nson, eac pr nspec or
~ iC/Vy
-'date signed date signed Approved by.~
~
~
~
R.
R. Keimig, Chief Reactor Projects Section No.
1, R08NS Branch date signed
date signed Ins ection Summar
Ins ection on Januar 29-31, 1979'e ort No. 50-244 79-02
~g<<d:
R f, df P
f f'P P
f f
P f
ff,dg outage, including major maintenance, modifications and critical path items.
The inspection also included a tour of the facility.
The inspection involved 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> on site by one NRC regional. based inspector.
Results:
No items of noncompliance were identi fied.
7'90408 00gg Region I Form 12 (Rev. April 77)
P
DETAILS Persons Contacted
- Mr. H.
Mr.
D.
- Mr. J.
Mr. T.
- Mr. T.
- Mr. J.
Mr. C.
- Mr. B.
- Mr. S.
- Mr. J.
Backus, Operations Supervisor Hamelink, Maintenance Supervisor LaRizza, Technical Engineer Marlow, Cadet Engineer Myer, Nuclear Engineer Noon, Assistant Plant Superintendent Peck, Operations Engineer Snow, Plant Superintendent Specter, Maintenance Engineer St. Martin, Liaison Engineer The inspector also interviewed other licensee employees during the course of the inspection, including members of the operations, maintenance and technical staff.
- denotes those present at the exit interview.
Refuelin Procedures The licensee has contracted the Nuclear Steam System Supplier (NSSS),
Hestinghouse Electric Corporation, to perform refueling activities including removal of the lower core intervals.
The NSSS has chosen to utilize their own procedures rather than the facility's procedures to accomplish the work.
Copies of these procedures were not available on site for the inspector's review.
The inspector requested that a copy of the procedures be sent to the regional office for review to expedite review.
The inspector stated that the procedures must.be reviewed, in accordance with the requirements of the Technical Specification, Section 6.8.1, prior to implementa-tion.
In -addition, all core alterations shall be directly super-vised,by an NRC licensed Senior Reactor Operator in accordance with Technical Specification, Section 6.2.2.d.
The licensee concurred with the inspector's comments and stated
. that a copy of the NSSS refueling procedures would be sent to NRC:RI as soon as they are availabl P
3. 'uta e Schedule Includin Critical Path Items The inspector reviewed the licensee's proposed outage activities including the schedule for accomplishment.
The following is the refueling outage schedule as of February 2,
1979:
Receipt and inspection of new fuel, February 6-9, 1979.
Shutdown and cooldown, begin general preparations for outage, February 10, 1979.'repare steam generators for inservice inspection, February 11-14, 1979.
Conduct eddy current testing and preparations for refueling, February 14-20, 1979.
Completely defuel for lower vessel internals removal, (routine in-service inspection)
February 22-26, 1979.
Remove lower vessel internals for reactor vessel inservice inspection (ISI), February 26, 1979.
Perform reactor vessel ISI, February 26-March 8, 1979.
Reload core, March 9-12, 1979.
Head reinstallation and restoration from refueling, March 12-17, 1979.
Commence filling and venting of reactor coolant system, March 17-18, 1979.
Perform preventive maintenance on 814 bus and switchgear, March 18, 1979.
Perform safety injection functional test, diesel generator operation and safeguards systems realignment, March 18-21, 197 Perform preventive maintenance on 812 main station transformer, March 22, 1979.
Commence heatup to 200',
March 22, 1979.
Heatup to 340'
in preparation for system hydrostatic test, March 23, 1979.
Perform ISI hydrostatic test of reactor coolant system, March 23',
1979.
Heat up plant to hot standby (547'),
March 23, 1979.
Conduct control rod drop tests, March 24, 1979; Perform control rod position indication calibrations and control rod exercise tests, March 25, 1979.
Perform reactor physics testing, March 26-27,, 1979.
Commence secondary side heatup and place the main turbine on line, March 27, 1979.
The inspector had no questions regarding the schedule.
4.
Ma 'or Modifications To Be Performed Durin Outa e
.
a ~
The inspector reviewed the following planned modifications:
(1)
Rod Control Insertion Limit Circuitr Modification:
Provide a stable high current limit by adding a medium current selector to eliminate nuisance alarms caused by noise at upper rod travel.
- Circuitry change does not alter original design characteristics or change any
'resent operating limit.
(2)
J-Tube Modification To Feed Rin s:
Install J-tubes on top of feed ring in the steam generators and eliminate bottom holes by plugging.
This modification is to prevent feed ring from draining on severe transients such as on reactor trips when level in the steam generators shrink rapidly and create a water hammer due to the interface of steam condensing rapidly in feed ring and subsequent introduction of cold feed wate F
(3) ~5t F
I Pit M diff': I t
ddt ti skid mounted pump and heat exchanger with temporary connections to existing permanent piping to increase cooling capacity due to higher than normal temperatures expected as a result of unloading a full core in the pool.
(4)
Reactor Coolant Pum Seal B
ass Modification:
Relocate piping and supports to change seal bypass line from lower flange connection to upper flange connection to eliminate a
aP when venting through the seal bypass line causing a
sufficient aP to possibly tilt the
seal ring.
(5)
Volume Control Tank Level Modification:
Eliminate the existing mechanical linkage that transfers the rotary motion to'inear, by installing a direct electrical connection for more accuracy and stability.
(6)
Removal of Part Len th Control Rods:
Remove the part length control rods from the cor e; install and seal weld anti-rotational devices in the motor tube housings to prevent shaft movement by gravity via the roller nuts.
b.
The inspector.'s.findings as a result of the review of the above modifications are as follows:
(1)
All of the above modifications were reviewed pursuant to the requirements of 10 CFR 50.59.
(2)
Except as noted below, procedures for the performance of the above modifications were reviewed by the onsite safety committee and approved for implementation by the Plant Superintendent.
(a)
Modification a..(5), above; Procedures are in draft form awaiting additional information from the engineering department; and, materials necessary for the modification are riot yet available.
(b)
Modification a.(6) above; Procedures are in draft form awaiting review by the POR >lith the exception to items (a) arid (b) above, that will be inspected on a subsequent inspection, the inspector had no questions on these modifications.
5.
Maintenance The inspector reviewed, on a sampling basis, the following procedures:
A-36, Station Holding Rules, Revision ll, May 25, 1978.
M-ll.8B, Reactor Coolant Pump - Seal Inspection and Service-Mechanical, Revision 7, July 25, 1978.
M-11.8G, Reactor Coolant Pump Post Maintenance Operational Check, Revision 3, September 23, 1976.
M-ll.12.1, Safety Injection Pump Mechanical Inspection, Revision 2, June 26, 1978.
M-48.1, Isolation and Restoration of Bus 813, Revision 0, November 1, 1977.
M-48.2, Isolation of Bus bl4, Revision 6, April 22, 1977.
M-50. 1, Isolation of 812 Transformer, Revision 4, March 13, 1978.
S-2 1B, Reactor Coolant Pump - Isolation for Maintenance, Revision 0, April 12, 1978.
The above procedures were selected on the basis of the associated maintenance activities scheduled during the refueling outage.
The above procedure review was performed to verify the following:
Format and content are in accordance with the guidelines set forth in ANSI N18.7-1976..
Review and approvals are in accordance with Technical Specifi-cation requirement Contain provisions for administrative. approvals for removing the system from service'and returning it to service.
Contain provisions for testing following maintenance.
Contain provisions for assuring that valves, breakers etc.
are aligned for normal service.
Contain hold points for inspection/audit and signoff by QA/gC or other licensee personnel.
No items of noncompliance were identified.
6.
~Fili i At various times during the period of January 30 and 31, 1979, the inspector conducted tours of the following accessible plant areas:
Auxiliary Building Turbine Building Control Room Outside Peripheral Areas During the inspection tours, observations relative to the following items were acceptable:
plant housekeeping and cleanliness; posting of radiation ar eas, access control, and currency of survey; security access controls; control room manning and assignment of licensed operators pursuant to the Technical Specifications; and, No selected monitoring instrumentation - operability and para-meters within license limits.
items of noncompliance were identifie.
Exit Intervi ew The inspectors met with licensee representatives (denoted in para.-;
graph 1) at the conclusion of the inspection on January 31, 1979.
The inspector'ummarized the scope and findings of the inspectio I (f