IR 05000272/1979010
| ML18079A529 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/04/1979 |
| From: | Caphton D, Kalman G, Tanya Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18079A528 | List: |
| References | |
| 50-272-79-10, 50-311-79-22, NUDOCS 7907110544 | |
| Download: ML18079A529 (10) | |
Text
...
U.S. NUCLEAR REGULATORY COMMISSION OF~ICE OF INSPECTION AND ENFORCEMENT
~
Region I Report N /79-20 Docket N /50-311 License No. DPR-70/CPPR-53 Priority------
Category _ _..c ____
_
Licensee:
Public Service Electric & Gas C Park Place Newark, New Jersey 07101 Facility Name:
Inspection at:
Salem Nuclear Generating Station Unit 1 & 2 Hancocks Bridge, New Jersey 27-28, 1979 Inspectors:
Approved by:
.1/-' ~
-z..,..-
D.. L. Caphton, Chief, Nuclear Su port Section No. l, RO&NS Branch Inspection Summary:
Ins ection on March.20-22, 1979 and March 27-28, 1979 Combined Re art No /79-10 and 50-311/79-20 Areas Ins ected:
Routine, unannounced inspection by regional based inspectors of Unit l the containment integrated leak rate test procedure; surveillance of pipe supports and restraints; preparations for refueling ; and licensee action on pre~
vious inspection findings; (Unit 2) licensee action on previous inspection finding The inspection involved 56 inspector-hours (Unit 1 - 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />, Unit 2 -
13.hours) on site by two NRC regional based inspector Results:
No items* of noncompliance were identifie Region I Form 12 (Rev. April 77)
-i
--j
. !
'
- DETAILS Persons Contacted The below listed technical and supervisory personnel were contacte Public Service Electric and Gas Company B. Canfield, Maintenance Supervisor G. Duncan, !SI Maintenance Engineer L. Fry, Senior Performance Supervisor
- R. Griffith, Senior Staff Engineer, QA R. Lombard, Operations Engineer
- H. Midura, Manager Salem Generating Station
- M. Metcalf, QA Engineer, Resident Group
- E. Meyer, Project QA Engineer
- J. Nichols, Reactor Engineer
- J. Stillman, Station QA Engineer
- J. Zupko, Chief Engineer U.S. Nuclear Regulatory Commission D.Caphton, Chief, Nuclear Support Section No. l
- denotes those present at the exit interview on March 22, 197 ** denotes those present at the exit interview on March 28, 197 The inspectors also talked with and interviewed other members of the engineering and technical staff.
Licensee Action on Previous Inspection Findings
{Closed.) UnresoliVed Item (272/79-01-02):
The inspector reviewed Revision 13 {dated March 1979) of M16E 11Containment Isolation Type B and C Tests.
This revision requires that the Type Band C leakage surrmation be calculated using the higher leak rate of two series con-tainment isolation valves in one penetration. The procedure also requires a comparison of the present leak rate to the previously determined leak rate for valves six inches and larger to monitor potential valve deg*radatio This item is considered resolved.
,
{!)
- _/
(Closed) Unresolved Item (272/79-01-03):
The inspector reviewed Surveillance Procedure SP (0) 4.0.5-V 11 Inservice Testing - Valves 11,
Revision 4. This procedure requires the check of valve position in-dication required. by IWV-3300 for valves which are inaccessible for direct observation during plant operation. This item*iis considered resolve ;
(Closed)
Unresolved Item (272/79-01-04): Surveillance Procedure SP (0) 4.0.5-V Revision 4 requires that dual function check valves be tested in both the open and shut directio Detailed measurements of normally closed check valves, as required by paragraph rnV-3520 (b)(2), cannot be made due to lack of system instrumentatio In the Pump and Valve Test Program Twenty Month Update submitted February 9, 1979, the licensee has requested exemption from making these measurement These items are considered resolve (Closed)
Unresolved Item (272/79-01-05): Surveillance Procedure SP (0) 4.0.5-V has been revised to include maximum stroke times for all power operated Category A and B valves. This item is considered resolve. (Closed) Unresolved Item (272/79-01-06): The inspector reviewed Revision 3 of SP (0) 4.0.5-V (Maint),
11 Inservice Testing-Valves 11 *
The resolution of each subpart of the unresolved item is. as follow (1)
The revised procedure specifies that valves on which maintenance is performed or valves which fail stroke time criteria are to be tested under this procedur (2)(3}-}:.. "Ehe format-,o.f:.the running log has been revised and is now main-tained by valve type and associated testing requirement (4)
The format of the test sheets has been changed to provide a space for the shift supervisor to indicate his review for each individual valve tes (Closed)
Unresolved Item (272/79-01-07): The inspector reviewed Revision 6 of SP (0) 4.6. Containment System - Primary Containment
and determined that valve ISA 905 had been added to the procedur The licensee also performed a review and determined that all applicable valves are included in SP (0) 4.6...
- ~
r)
i--**
'
(Open) Unresolved Item (272/79-01-01):
The inspector reviewed SP (0) 4.0.5-P, "Inservice Testing - Pumps" Revision 4 and "Pump Allowable Test Ranges" dat The resolution of each subpart of the unresolved item is as follow *
(1)
Comparisons of operating pump data with appropriate acceptance criteria are now being conducted as required by Subsection IWP 320 This item is considered resolve (2)
Reference values for pump parameters have been established in accordance with Subsection IWP 311 This item is considered resolve (3)
Limits for bearing temperatures and inlet pressures have been specified as required by Subsection IWP-321 This item is considered resolve (4) Thermocouples used for determining bearing temperatures not been calibrated as required by Subsection IWP-411 licensee representative has committed to complete these brations by June l, 1979. (Open)
have A
cali-(Closed) Unresolved Item (311/78-29-04):
The inspector reviewed SUP-DTP-30-LRT-2 11Reactor Containment Type C Leak Rate Test 11 through Change 1 The resolution of each subpart of the unresolved item is as follow (1)
10 CFR 50 Appendix J and the above procedure require draining of both sides of a containment isolation valve prior to testin The inspector reviewed valve lineups for penetrations 18, 49, 54 and a random sample of other penetrations to ensure complete drainin No discrepancies were discovere This item is considered resolve (2)
The inspector reviewed va1ve lineups for penetrations 49, 54, E22 and a random sample of other penetrations to ensure the downstream side of the valve under test was vente No dis-crepancies were discovere This item is considered resolve (3) All tests were conducted using the primary test metho No procedural changes were required. This item is res*olve (Closed) Unreso1ved Item (311/79-01-01):
The following items are resolved based on a review of SUP 48 11 Preservice Testing of Pumps and Valves" and discussions with licensee personne SMII No. 17 has been cancelled and replaced by SUP 4 _j
'-'
5 SUP 48 has been revised to include maximum stroke times for all Category A and B valve SUP 48 has been revised to require testing of dual purpose check valves in both the open and closed direction Detailed measurements of normally closed check valves, as required by paragraph IWV-3520 (b)(2), cannot be made due to lack of system instrumentatio The licensee has requested exemption from making these measurement SUP 48 has been revised to require a check of valve position indicators for inaccessible valve The testing of Category C relief valves has been incorporated into SUP 4. The pump bearing temperature stabilization criteria of IWP-3500 have been incorporated into SUP 4 The revised SUP 48 ca 11 s for the measurement of a l1 required pump bearing temperatures and vibration dat (Closed) Unresolved Item (311/78-56-01):
Licensee fuel handling building crane inspection reports were reviewed and no discrepancies were identified. This item is now resolve (Closed)
Unresolved Item (311/78-56-02): Licensee* reevaluated and augmented the fuel handling bui.lding fire protection syste The fuel handling building was subsequently inspected by an NRC fire protection specialist (311/79-05) and no discrepancies were identifie *This item is now resolved.
. Canta inment Integrated Leak Rate Test ( CILRT) Procedure General The inspector reviewed a draft version of the CILRT procedure SP (0) 4.6.1.2, "Containment System - Type A Integrated Leak Rate Test Unit NO. 1.
for conformance with 10 CFR 50 Appendix J (App.J), ANSI N45.4, Salem 1 Technical Specifications, and current NRC position With the exception of the below items the inspector had no further questions on the draft procedure.
...
!
(f)
! - --<
\\ (
- -~ CILRT Procedure The below items associated with the CILRT procedure are collectively designated as open item (272/79-10-01).
(1)
Test Duration The procedure has a provision which allows the test to run less than 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ANSI N45.4 requires a test duration of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless it can be shown that an accurate leakage rate can be obtained from a shorter test. _It is the NRR'*S position that a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test is required to insure an accurate and representative leakage rate determinatio (2)
Acceptance Criteria Section V.B. 3 of Appendix J specifies the requirement for analysis and interpretation of CILRT results. The in-spector also informed the licensee of the NRR position regarding the acceptance criteria of the CILR The measured leakage rate at the 95% upper confidence level plus required additions must be less than 0.75 L (3)
Data Evaluation Technique The procedure does not specify a data evaluation metho The inspector informed the licensee that the NRC accepts the mass point data evaluation technique as the preferred metho (4)
Leak Repair There is no warning or prohibition statement in the procedure against repairing leaks after the containment is pressurize If leakage is discovered during the test, which could cause the test not to meet the acceptance criteria, the offending leak may be isolated and the test continued provided that:
(a)
(b)
The penetration is locally testable and is given a local leak rate test (LLRT) both before and after repair; The pre-repair LLRT results are added to.the CILRT results to determine the success of the initial CILR attempt (as found leakage); and (c)
The post repair LLRT results are added tq the c-ILRT results to determine the success of the final CILRT attempt (as left leakage).
.. _
(5)
Events Log ANSI N45.4 requires that a dated log of events and pertinent observations be maintained during the test. This is currently not required in the procedur (6)
Atmospheric Data The current procedure has a data sheet with space to record atmospheric data, however, the exact data to be recorded is not specifie ANSI N45.4 requires that atmospheric pressure and ambient temperature be recorded hourly durin the tes (7)
Absolute Values 10 CFR 50 Appendix J paragraph III.A.3.(c) requires that leakage rates be calculated using absolute values corrected for instrument error. The procedure presently does not re-quire that calculations be made using corrected dat (8)
Containment Volume Changes Volume decreases of containment due to level increases in the reactor coolant system and the containment sump mask containment leakag The measured leak rate must be con-servatively compensated for this volume chang The proce-dure currently measures reactor coolant system level but does not require analysis for correcting the measured leak rate.* Containment sump level changes are not presently requi~ed to be recorded..
(9)
Volume Weighting Factors Temperature (RTD) and dew point instrument volume weighting factors are not available in the current procedur There is also no plan in the procedure as to how these factors will be reassigned if instrumentation is lost due to failur (10) Venting and Draining Systems which are not drained and vented as required by Appendix J paragraph III.A.l.(d) must have their containment isolation valve Type C test leakage added to the Type A test*
measured leakage prior to comparison with the acceptance criteria4 There is no indication in the procedure which systems are in this *categor "*
I, i
(11) Data Rejection During the CILRT outlying data may be rejected provided definitive data rejection criteria have been establishe Currently, there are no such criteria in the procedur.
Preparation for Refueling Scope Preparatory activities and procedures related to the forthcoming refueling were reviewe Fuel vendor documentation and licensee inspection reports associated with the receipt of 40 new fuel assemblies were reviewe Refueling procedures were reviewed for compatibility with technical specifications and for com-pliance with applicable standard Documents Reviewed Procedure I-2, Rev. 8, Refueling; NRC Form 741 completed by fuel vendor for 40 fuel assemblies; Fonn 54990, Fuel Assembly Inspection, completed by licensee; Form 5499-1, Fuel Receiving Record - Container Report, completed by license Findings The inspector identified no discrepancies during the review of documents associated with the receipt of new fuel assemblie The content of the refueling procedure was compared to the guidelines set forth in ANSI 1 On the basis of this review, the inspector identified several items which were not addressed by the procedur (l) *One refueling prerequisite condition, the requirement for a RHR loop to be in operation, was not listed under the initial condition section of the procedur (2)
The requirement for continuous monitoring of source range neutron instrumentation during core alterations was not
- addressed.
-I i
~---)
':
i ---**
i (3)
Post refueling core verification procedures were not addresse Licensee representatives agreed to add the three items listed above to the ref ue 1 i ng procedure. This matter wi 11 be reviewed during the refu~ling inspection and is considered unresolve (272/79-10-02)
The. inspector expressed concern over the potential for misuse of the new fuel elevator to raise an irradiated fuel assembly from the spent fuel poo Licensee representatives agreed to evaluate whether it was mechanically possible to transfer a fuel assembly from the spent fuel pool to the new *fuel elevato If necessary, administrative controls will be established to decrease the likelyhood of such an even This matter is an inspector follow-up item (272/76-10-03).
Licensee representatives agreed to review refueling related procedures to ascertain that prior to resumption of fuel move-ment following an interruption of refueling operations, all refueling prerequisite condit~ons will be reverified in the course of following existing surveillance schedule Prerequisite conditions not included in existing checks will be added to the refueling procedure if any possibility exists that they may be overlooked following an interrruption in refueling operation This matter is an inspector follow-up item {272/79-10-04).
Pipe Supports and Restraints Scope The inspection consisted of a document review of hydraulic snubber inspection procedures and report The inservice inspection program for pipe support systems was reviewed and the progress of the licensee's inspection effort was discussed with cognizant personne Documents Reviewed Long-Term Inservice Examination Plan for Class 1, Class 2, and Class 3 Components and Systems at Salem Generating Station, Unit,
- '
-
l
- Procedure M 118, Rev. 4, Hydraulic Snubber Procedure M 178, Rev. 4, Coded Component and Pipe Support Visual Examinatio Procedure Examinatiori Qualification and Certification Program, Rev. *Snubber Visual Inspection Reports dated 3/10/77 and 1/13/7 Findings Except as noted below, the inspector identified no problems with the pipe support and restraint inspection progra The licensee snubber visual inspection procedure does not include the requirement to measure the snubber piston position to ascertain that the piston movement would not bottom during normal thennal induced movemen Licensee representatives stated that Technical Specifications do not specifically address the requirement for piston position measurement during the visual inspection and that this additional step would impose additional work with questionable benefit considering the limited and unique application of the hydraulic snubbers. This matter will be designated an inspector follow-up item pending inspection of the snubbers and their speci-fications during the refueling shutdown. (272/79-10-05).
Unresolved Items Items about which more information is required to *detennine accepta-bility are considered unresolve Paragraph 4.c. of this report contains unresolved item.
Exit Interview At the inspection's end the inspectors held a meeting (see Paragraph l for attendees) to discuss the inspection scope and finding The unresolved items were identified.