IR 05000311/1979008
| ML18078B106 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/13/1979 |
| From: | Baunack W, Conte R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18078B104 | List: |
| References | |
| 50-311-79-08, 50-311-79-8, NUDOCS 7903300007 | |
| Download: ML18078B106 (12) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Report N /79-08 Docket N Region I License No. _c_P_PR_-_5_3 __
Priority-------
Public Service Electric and Gas Company Category __
B_l ___ _
Licensee:
80 Park Place Newark, New Jersey 07101 Facility Name:
Salem Nuclear Generating Station, Unit 2 Hancocks Bridge, New Jersey Inspection at:
Inspection conducted: January 22-30, 197~
Inspectors: kJ. jJ. ~~{.,.
W. H. Baunack, Reactor Inspector
. ~~fi~Jr=lnspector
~ f f / "'JjL1-L<.,.,
d.!?~t Inspector
- Approved by:...:::_~*-----.------
H. B. Kister, Chief, Nuclear Support Section No. 2, RO&NS Branch Inspection Summary:
2/J :i.) 7<).
'date 'signed
'LJ) \\ vJ l S Inspection on January 22-30, 1979 (Report No. 50-311/79-08)
Areas Inspected: Routine, unannounced inspection by regional based inspectors
- of facility procedure scope; station plant manual operating instructions -
Unit 2, and facility procedure format and content in the areas of general plant operating procedures; procedures for startup, operation, and shutdown of
safety-related systems, and procedures for combating emergencies and other significant event The inspection involved 156 inspector-hours onsite by three regional based NRC inspectors and five hours onsite by one NRC superviso Results:
No i terns of noncomp l i ance were observe *
7903300007 Region I Fonn 12 (Rev. April 77)
':~
"
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DETAILS Persons Contacted Public Service Electric and Gas Company
- L. Fry, Senior Performance Department Supervisor (Instrument & Control)
- S. LaBruna, Maintenance Engineer
- B. Leap, QA Supervisor
- D. Lyons, QA Specialist
- M. Metcalf, QA Engineer, Resident Group
- M. Murphy, Associate Engineer - Operations J. Robertson, Senior Maintenance Supervisor
- J. Ronafalvy, Engineer-Operations R. Scalletti, Safety Supervisor R. Si'lverio, Assistant to Manager
- J~ Stillman, Station QA Engineer
- J. Zupko, Jr., Chief Engineer USNRC
- L. Norrholm, Resident Reactor Inspector H. * Kister, Chief, Nuclear Support Section No. 2, RO&NS Branch The inspectors also interviewed other applicant employees, including members of the Technicql and Engineering Staff, Maintenance Department personnel, and general office personne * denotes those present at the exit intervie.
Purpose of Inspection To confirm that facility procedures are prepared to adequately control safety related operations within applicable regulatory requirement. * Facility Procedures Scope The inspectors reviewed the applicant's current index and file of procedures to verify adequate coverage in accor9ance with the requirements of Regulatory Guide l.33; Revision 2, February 1976, Appendix A, (R.G. l.33) in the following pro-
.. cedural categories:
- Administrative General Plant Operating Procedures for Startup, Operation and Shutdown of Safety-Related Systems Emergency and Other Significant Events Abnormal and Alarm Conditions Maintenance Control of Measuring and Test Equipment Surveillance The inspectors noted that the applicant's established proce-dures index in general covered all activities listed in.33 as required by proposed Technical Specification, Section 6.8. 1. A number of areas were identified in which additional procedures must be written or existing procedures modified in order to fully meet requirements, unless these requirements can be shown to be satisfied in existing procedure These areas were identified as follows:
(1)
Operation at Hot Standby as required by paragraph 2.d of R. G. 1. 3 (2)
Pressurizer Pressure and Spray Control System, as re-quired by paragraph 3.j of R.G. 1.3 (3)
Reactor Control and Protection System, as required by paragraph 3.u of R.G. 1.3 (4)
Loss of Condenser Vacuum, as required by paragraph 6.e of R.G.. l. 3 (5)
Loss of Service Water (present procedure covers only partial loss of service water), as required by paragraph 6.g of R.G. 1.3 (6)
Loss of Protective System Channel (present procedure covers only loss of nuclear instrumentation), as required by paragraph 6.k of R.G. 1.3 (7)
Malfunction of Pressure Control System, as required by paragraph 6.t of R.G. 1.33.
The applicant stated new procedures would be prepared for the above items, or incorporated into existing procedures as appropriate. This will be accomplished prior to core load. This item is open pending completion of the applicant's action as stated above and subsequent NRC:RI revie ( 311 /79-08-01)
(8) Several procedures were not yet available for review for certain proposed Technical Specification requirement This was apparently due to a variety of reasons, such as, procedures still under preparation, in the process of being typed, certain Technical Specifications had not yet be~n finalized, o~ new requirements for which procedures had not yet been prepare Procedures were not available in the following areas:
4.l.1..1.3~5 4.3..4.9..5.1.d'
4.5..5.. 6. 1. 2. a-f 4.7..7..7.6.1.b-d 4.7.7.1.b-d 4.7.10.1.1,2,3 4.7.1.7.10.4.
4.7.11 4.8.1.1.2.a & b 4.8.2.3.2.b & c 4.8.2.5.2.b & c 4.8..8.3..9.12 The applicant stated that all proposed Technical Speci-fication required surveillances would have procedures written, reviewed, and approved prior to core load with the possible exception of certain long term (18 mo. or greater) surveillance requirement This item is open pending completion of the applicant's action as stated above and subsequent NRC:RI revie (311/79-08-02)
(9)
R.G. 1.33, Revision 2, 1978, paragraph 3, and ANSI 18.7 -
1976Property "ANSI code" (as page type) with input value "ANSI 18.7 -</br></br>1976" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., paragraph 5.3.3, in reference to system operating procedures require, in part, that instructions for filling, venting, and draining systems are to be delineate The inspector observed that the subject instructions were provided for systems that are frequently drained/filled during the operating cycle; such as the Reactor Coolant Syste However, operating instructions for other systems listed in R.G. 1.33 did not have instructions of this type delineated; such as, Auxiliary Feedwater, Component.
Cooling, Service Water, and F~edwate * *.
The applicant's representative stated that many systems, such as Component Cooling, are not totally drained in an operating cycle unless it is for maintenanc Further, it was stated that, based on Unit l experience, if main-tenance is conducted, it is on a component/section of the system which is isolable, and that draining and subse-quent fill and vent is handled on a case by case basis in accordance with the maintenance progra For initial criticality Unit 2 systems will be filled and vented per the Startup Progra The inspector acknowledged the applicant's comments and stated that maintenan~e procedures do not specifically address operations responsibilities for valve manipula-tions during major maintenance activities requiring draining, filling and ventin The ~pplicant's repre-
. sentative stated that this area would be reviewed and that either further. administrative cont~ols would be established, or a. generic procedure to cover the area would be develope It was further stated that this would be completed within six months after ~ore loa This is open pending completion of the applicant's action and subsequent NRC:RI review (311/79-08-03).
(10) The inspectors noted that in order to be in compliance with proposed Technical Specification 6.5.l.6.a, it appeared the following existing procedures should be Station Operations Review Committee (SORC) reviewe III. 1.3.l, Turbine Generator Operation. (Ref. R.G. 1.33 Paragraph 2.e)
IIT. 2.3. l, Main Reheat, Turbine Bypass Steam Warmu (Ref. R.G. 1.33, Paragraph 3.i)
III. 9.3. l to 3, Feedwater System Procedures (Ref..33, Paragraph 3.k)
The applicant stated that these procedures would be SORC reviewed prior to core load. This item is open pending completion of the applicant's action as stated above and subsequent NRC:RI revie (311/79-08-04)
- ,, '--4 6 During this review, the inspectors noted that many procedures, or sections of procedures, required by R.G. 1.33 remained to be properly reviewed, approved and/or issue The applicant's representative stated that the following procedures/instructions are to be issued prior to core load or as otherwise noted
Station Plant Manual (SPM) Operating Instructions as
- discussed in Paragraph All SPM Alarm Procedures; Operations Department Surveillance. Procedure except long range requirements as noted in Paragraph 3.b(8);
Mode 3 and Mode 4 Required Surveillance Check Off Lists of QI I-3.2, Cold Shutdown to Hot Standb These lists were not available for review to verify that operability of the 500 KV and 13 KV Systems for plant startup is checked; Maintenance Department Manual Procedures requiring re-vision prior to March l~ 1979; Fire Fighting and Organization Manual and associated Surveillance Procedures due to be issued by February 20, 197 This is open pending completion of the applicant's action as noted above and subsequent NRC:RI review (311/79-08-05). Station Plant Manual (SPM) Operating Instructions - Unit 2 The inspector observed that many OI's were marked on the SPM Pro-cedures Status Index as needed for core load and that they have not been issued as ye Some OI's, which were not issued, were not marked for core load but it appeared to the inspector those proce-dures would be neede This applies to the following procedures:
II 1~3.5, RC Leak Detection; II - 4.3.l, Safety Injection System - Normal Operation;
II - 5.3.1, Fill and Vent the CS System; II - 9.3.l, Manipulation Crane; II - 9. 3. 2,. Fuel Transfer System; II - 9.3.3, Control Rod Shaft Unlatching Tool; Il - 9.3.5, Thimble Plug Handling Tool; II - 9.3.10, RCC Changing Fixture; II - 9.3.11, Burnable Poison Rod Assembly Handling Tool; II - 9.3.12, New Fuel Assembly Handling Fixture; II - 9.4.l, Fuel Transfer System; II -
8.3.3~ Filling the Reactor Refueling Cavity; II - 8.3.4, Draining the Reactor Refueling Cavity; II - 10.3.2, Gas Analyzer Operation; II - 1L3.l, Waste Holdup Tanks - Normal Operation; II - 14.3.l, Containment Drains System Operation; II - 15.3.l, Hydrogen Recombiner - Normal Operation; II - 15.3.2, Personnel Locks and Containment Entry; II - 17.3.l, Auxiliary Building Ventilation Operation; III - 13.3.l, Draining the Steam Generator; IV - 1.3.lA and B, 500 KV - Normal Operation; IV - 3.3. l 13 KV - Normal Operation;
..
IV - 4.3.3 A and B, 4 KV Group Busses - Normal Operation;
- IV~ 5.3.1, Battery Ground Detection; IV - 5.3.2, Battery Charger Operation; IV - 6.3.2, Operation of the Axial Flux Deviation System; IV - 7. 3. 1, Flux Mappi_ng System - Norma 1 Opera ti on; IV - 11.3.1, Area Radiation Monitors - Normal Operation; IV - 11.3.2, Process Fitters Radiation Monitors-Normal Operation; IV - 11.3.3, Process Radiation Monitor-Normal Operation; IV~ 11.3.4, Operation of the Control/Plant Ventilation Sampler; V - 1.3.1, Service Water - Normal Operation; V - 3.3.1, Fire Protection*System Operation; V - 3.3.2, Refilli_ng Liquid Foam Star.age Tank; V - 3.3.4, Notification of Impairment to the Fire Protection
_ System; V - 9.3.1, Chilled Water System - Normal Operatio The applicant 1s representative stated that these procedures will.be issued prior to core load and the remaining system operating instructions would be issued prior to initial criticalit *
This is open pending licensee completion of action as noted above and subsequent NRt:RI revie NRC:RI will review this area in conjunction with those items (311/79-08-05) in Paragraph.
Facility Procedure Format and Content The inspectors reviewed the below listed procedures on a sampling basis to verify the following:
Technical content was adequate to assure satisfactory performance of intended function Format was in accordance with ANSI Nl8.7 and the licensee's administrative control b; The following procedures were reviewed:
General Plant Operating Procedures
- I - 3.1, Refueling to Cold Shutdown, Revision 0, June 5, 197 I - 3.2, Cbld Shutdown to Hot Standby, Revision 0, October 27, 197 I - 3.3, Hot Standby to Minimum Load, Revision 0, November 27, 197 r - 3.4, Power Operation, Revision 0, October 20, 197 I - 3. 5, Minimum Load to Hot Standby, Revision 0, July 17, 197 I - 3.6, Hot Standby to Cold Shutdown, Revision 0, October 27, 197 I - 3.7, Cold Shutdown to Refueling, Revision 0, October 20, 197 Procedures for Startup, Operation and Shutdown of Safety-Related Systems II - 1.31, Reactor Coolant Pump Operation, Revision 0, May 8,
. 197 II - 1.3.4, Filling and Venting the RCS, Revision 0, May 12, l 97 II - 1.3.6, Draining the Reactor Coolant System, Revision 0, July 12, 197 *
II - 3.3.li Establishing Charging, Letdown, and Seal Injection Flow, Revision 0, May 4, 1978. *
- II - 3.3.2, Operating the Charging Pumps, Revision 0, May 4, 197 II - 3.3.5, Boric Acid Solution Preparation and Transfer, Revision 0, September 26, 197 II - 3.3.8, Rapid Boration, Revision 0, July 28, 197 I - 3.3.6, Boron Concentration Control, Revision 0, July 17, 197 Il - 3.3.7, Boric Acid System Normal Operation, Revision 0, September 26, 1978. *
II - 7.3.l, Component Cooling System Makeup and Chemical Addition, Revision 0, May 11, 197 II - 7.3.2, Component Cooling System - Normal Operation, Revision 0, May 11, 1978. *
- II - 16.3.1, Containment Ventilation Operation, Revision 0, October 27, 197 II - 17.3.2, Control Room Venttlation Operation, Revision 0, October 27, 197 III - 2.3.l, Majn, Reheat, Turbine Bypass Steam Warmup, Revision 0, October 27, 197 III - 9.3.1, Placing Feed and Condensate System in Service, Revision 0, November 2, 197 III - 10.3.l, Auxiliary Feedwater System Operation, Revision 0, November 2, 197 III - 15.3.1, Demineralized Water Transfer - Normal Operation, Revision 1, October 18, 197 (Procedure common to both units)
IV - 4.3.4, 4KV Vital Susses - Normal Operation, Revision 0, October 27, 197 IV - 8.3.1, Rod Control System - Normal Operation, Revision 0, October 27, 1978.
IV - 6.3.1., Operation of Nuclear Instrumentation System, Revision 0, October 27, 197 IV - 16.3.1, Emergency Power - Diesel Operation, Revision 0, November 2, 197 Procedures for Combating Emergencies and Other Significant Events I -
4.1~ Flooding and/or High Wind Conditions, Revision 5, March 18, 197 I - 4.3, Reactor Trip, Revision 3, March 13, 197 I --4.4, Loss of Coolant (Leakage Greater Than Maximum Charging Flow), Revision 7, December 6, 197 I - 4.5, Loss of Reactor Coolant Pump and/or Flow, Revision 2,
_; March 7, 197 I - 4.8, Rod Control System Malfunction, Revision 4, October 18, 197 I - 4.9, Blackout, Revision 6, April 25, 197 I - 4.10, Control Room Evacuation, Revision 4, April 24, 197 I - 4.11, High Reactor Coolant Activity, Revision 2, April 24, 197 I - 4.12, Loss of Feedwater, Revision 1, April 24, 197 I - 4.14, Service Water System Malfunction, Revision 4, April 24, 197 I ~ 4.15, Loss of Component Cooling, Revision 2, April 24, 197 I - 4.16, Radiation Incident, Revision 4, December 6, 197 I - 4.17, Partial Loss of Reactor Coolant, Revision 2, April 24, 197 I - 4.18, Loss of Control Air, Revision 2, May 15, 197 I - 4.19, Malfunction - Nuclear Instrumentation, Revision 3, October 18, 197 I - 4.20, Failure of a Reactor Coolant Pump, Revision 4, April 28, 197 I - 4.22, Loss of Residual Heat Removal Shutdown Cooling, Revision 2, April 25, 197 I -* 4.23, Loss of Containment Integrity, Revision 2, April 25, 197 As a result of the review of procedures, a number of discre-pancies were identified by the inspectors in recently issued procedures and were discussed with the applican The appli-cant stated the subject discrepancies would be correcte To assure a more thorough review, all operatin.g and surveil-,
lance procedures issued for Unit 2 between-February l. 1979, and core load will receive, an additional_second level review by a knowledgeable individual. This second level review will be documente This item is open pending com-pletion of ~the applicant 1s action as noted above and subse-quent NRC:RI revie (311/79-08-06) Open I terns Open items are find_ings associated with documents/procedures that the applicant intends to use to implement regualtory requirement upon receipt of the operating licens Open items disclosed during the inspection are discussed in Pa~agraphs 2.b, 2.c, 4.c.and 5.c~ Exit Interview The inspectors met with applicant's representatives (denoted in Paragraph 1) at the conclusion of the inspection on January 30, 197 The scope and findings of the inspection were discusse Subsequent discussions on ~he findings occurred in a telephone conversation between Mr. Zupko and -Mr.. Baunack on February 1, -1979-..