ML18079A857
| ML18079A857 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/14/1979 |
| From: | Blumberg N, Kister H, Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18079A856 | List: |
| References | |
| 50-311-79-23, NUDOCS 7908280225 | |
| Download: ML18079A857 (19) | |
See also: IR 05000311/1979003
Text
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report *No. 50-311/79-23
Docket No. 50-3JJ
License ~o. CPPR-53
Priority --
Category
BJ:
Licensee:
Public Service Electric and Gas Company
80 Park Place
Newark, New Jersey O?l'Ol
Facility Name:
Salem Nuclear Generating Station, Unit 2
Inspection at:
Hancocks. Bridge, New Jersey
Inspection conducted:
March 29-30, April 4-6, and Apr~l 9-12, J979
Inspectors:
Approved by:
- lJ.JJ. 6~
W. H. Baunack, Reactor Inspector
(April 9-T6, 1979)
'ef, Nuclear Support
Section No. 2, Reactor Operations
and Nuclear Support Branch
date signed
date* signed
date sl9ned
s-/1rf/f'
date signed
G/;¥/7?
dfu Slgned
2
Inspection Summary
Ins ection on March 29-30, A ril 4-6, and A ril 9-12, 1979
Re ort
No. 50-311/79-23
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, alarm procedures, surveillance procedures, and
maintenance procedures; and applicant action on previo"usly identified. open
items.
The inspection involved 184 inspector-hours onsite by four regional
based NRC inspectors.
Results:
No items of noncompliance were identified .
DETAILS
1.
Persons Contacted
Public Service Electric and Gas Company
G~ Duncan, Mechanical,
Lead Engineer
Inspection, Examination and\\Test
\\
'
'
'
L. Fry, Seni.or Performance Department
and Contra 1)
Supervisor (I~strume~t
- W; Hunsinger, Resident QA
R. Lombard, Engineer, Operations
D. Lyons, QA Specialist
- H. Midura, Ma*nager, Salem Generating Station
- L~ Miller, Station Performance Engineer-
M. Murphy, Associate Engineer - Operations
F. Robertson, Maintenance Supervisor
- J .. Rona fa lvy, Engineer - Operations
A. Sea 1 ett i ., Safety Supervisor
- J. Stillman, Station QA Engineer
- J. Zupko, Jr .* Chi~f Engineer
USN RC
- L. Norrholm, Resident Reactor Inspector
The fnspectors also interviewed other applicant employees, including members
of the-Technical and Engineering Staff, Maintenance and Performance Depart-
ment p_ersonne 1 , Reactor Operators, and general -office personne 1 .
- Denotes those present at the exit i nte.rvi ew ..
2.
Licensee Action on Previous Inspection Findings
(Closed) Open Item (311/79-04-06):
Departmental procedures not in agree-
ment with a Station Administrative Procedure.
Administrative Procedure
(AP)-1 has been revised, r~quiring that whenever a new AP or a revision to
an AP is issued, each station department responsible for maintaining pro-
cedures shall complete Form AP-1-6, indicating that all required actions to
insure compliance with the new edition of the AP have_been completed.
(Closed) Open Item (311/79-04-04):
Documentation verifying placement of
jumpers.
Form AP-13.1. has been revised to include a signature block for
the supervisor in charge of verifying placement of jumpers.
4
(Closed) Open Item (311/79-04-10):
Operating/Special Orders.
AP-3, Station
Documentatian, has been revised, authorizing the use of the Operations
Directive Manual, Operating Department Memos and Night Order book at the
station.
Additionally, the distribution, review and approval requirements
as we 11 as the review frequency are set forth in AP-3.
(Closed) Open Item (311/79-04-05):
Maintenance Manual Procedure A-5 does
not reference temporary jumpers.-
A-5 has been revised to address both
temporary and permanent jumpers and is consistent with AP-13, Control.of*
Lifted Leads and Jumpers.
(Closed) Open Item (311/79-04-07):
Use of draft. copies of procedures.
Draft copies of procedures used by inspectors to verify compliance with the
requirements of ANSI Nl8.7-1976 and documented as drafts in Inspection
Report 79-04 have been properly revised and issued.
I
(Closed) Open Item (311/79-04-08):
Preventive.Maintenance Program.
Preventive maintenance for Unit 2 has been scheduled in accordance with th~
Inspect ion Order System in the same fas hi on as the Unit 1 program.
(Closed) Open Item (311/79-04-13):
Changes to valve line~ups. The appli-
cant is revising the va.l ve 1 i ne-up sheets to p 1 ace
11 auto
11 in the norma 1
position indication for automatic type valves, vice
11open 11 or 11closed11
which had been the case.
In this manner, a change need not be issued when
an automatic valve is realigned by an actuating signal.
(Closed) Open Item (311/79-04-12):
Dual unit applicability fo*r on-the-spot
changes.
AP-3 has been revised, requiring the initiator of a change to
determine if there is applicability to the other unit.
(Closed) Open Item (311/79-04-14):
Changes to Chemistry and Radiation
Protect ion procedures.
The Performance Department Manu.a T has been revised;
not allowing on-the-spot changes to be made to Chemistry or Radiation
Protection procedures.
(Closed) Open Item (311/79-04-17): - Incorporate controls for periodic
review.
The Performance Department Manual has been revised to includ~
requirements for the periodic review of the Instrument and Control (I&C),
Chemistry and Radiation Protection procedures which implement surveillance/
calibration requirements of Technical Specifications.
(Closed) Open Item (311/79-04-09):
Experience level requirements.
A-3,
Maintenance Department Training, has been revised requiring a Level I
individual to have a minimum of three years experience in one or more
crafts.
5
(Closed) Open Item (311/79-04-16):
Station Administrativ~ Procedures
(AP
1 s) periodic review.
The periodic review of AP's has been incorporated
into the Inspection Order System.
The review is to be documented on the
computerized Inspection Order Card.
(Closed) Open Item (311/79-04-18):
Periodk review requirements.
The
General Information Section of the Station Plant Manual has been revised to
address requirements for the periodic review of the General Plant and
Sys*tem Operating Procedures, Emergency A la rm Response and Survei 11 ance Test
(operations) Procedures.
(Closed) Open Item (311/79-04*19):
Format requirements .. The Station Plant
- Manual has been revised to include format requirements consistent with ANSI
N18.7-1976 for Operating Instructions and Emergency Procedures.
{Closed) Open Item (311/79-04-22):
Reactor Engineering Manual.* The Reactor
Engineering Manual and Operations Directive Manual have* been revised for
applicability to Unit 2 and have been revised.
(Open) Open Item (311/79-04-20) :.
Performance Department Manual (PDM).
The
PDM has been revised to include procedural format requirements with the
exception of. including acceptance criteria. This ite~ remains open pending
applicant action to. include the above procedural content requirement of
ANSI Nl8.7-1976 and subsequent NRC:RI review.
(Open) Open Item (311/79-04-01):
AP-2, Organization and Responsibility.
AP-2 has not yet. been revised to include the requirements of ANSI N18.7-
1976Property "ANSI code" (as page type) with input value "ANSI N18.7-</br></br>1976" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..
(Open) Open Item (311/79-04-02):
Quality Assurance Program.
AP-17, which
will incorporate the requirements of ANSI N18.7-1976, Section 5.1, has not
yet been issued.
(Open) Open Item (311/79-04-03):
Operator Responsibilities./ AP-5, which
will incorporate the requirements of-ANSI NlS.7-1976, Section 5.2.1, has
not been issued.
(Open) Open Item (311/79-04-11):
Night Order Book.
AP-5 has not yet been
revised to clarify that the Night Order Book is not intended to promulgate
Temporary Procedures.
(Open) Open Item (311/79-04-15):
Procedure Adherence.
AP-5 has not yet
been revised to address the procedure adherence requirements of ANSI Nl8.7-
1976, Section 5.2.2.
6
(Open) Open Item (311/79-04-21):
Refueling Instructions.
Refueling In-
structions have not yet been revised to reflect an approval status as
required by ANSI Nl8.7-1976, Paragraph 5.3.2(1).
(Closed) Open Item (311/79-08-03):
Filling, venting and draining proce-
dures.
The applicant has issued generic procedure OI I-3~9 to cover filling,
venting and draining of those systems which do not have specific procedures
for accomplishing those operations.
(Open) Open Item (311/79-08-01):
Procedures required by R.G.1.33.
The
following procedures were still in preparation at the conclusion of the.
inspection:
Operation at Hot Standby
Pressurizer Pressure and Spray Control System
Malfunction of Pressure Control System
The applicant stated that, (1) a specific procedure for Reactor Control and
- Protection System had'not been issued, as the system was covered adequately
by other procedures and, (2) that the Loss of Service Water. emergency
procedure had not been revised to include a ,complete loss of service water,
as this was not considered a credible accident due to system design.
The
inspector concurred with the above positions.
The above item remains .open
pending issuance of required procedures* and subsequent NRC:RI re~iew.
(Open) Open Item* (311/79-08-04):
Procedures requiring Station Operations
Review Committee approval.
The procedures specified are in preparation for
both Unit 1 and 2, with the exception that Feedwater System Procedures III-
9. 3. land III-9.3.3 have been reviewed and issued for Unit 1.
This item
remains open pending completion of applicant action and subsequent NRC:RI
review.
(Open) Open Item (311/79-08-02):
Proposed Technical Specification required
surve*n 1 ances.
Survei 11 ances, with frequency requirements 1 ess than 18
months, for which procedures have not yet been issued, are as follows:
4.1.1.5.b
4.1.3.5
4.3.3.7
4. 8.1.1. 2. b(l)
4.3..3.1
4.4.9.3.2.
4.5.3.2
4.7.6.l.d(3)
4.3.3.6.1
4.7.7.l.d(3).
4 .. 7 .10.1. la
4.7.10.3
4.3.3.6.2
The above surveillances includes proposed Technical Specification surveil-
lances is~ued during the course of the inspection .
' --
7
(Open) Open Item (311/79-08-05):
Procedures/Instructions remaining to be
issued.
Procedures remain to, be issued for alarm, general information, -
_
annunciators, overhead pane 1 s F, G, H, I, J and K, co.nso 1 e a 1 arms,
auxiliary annunciators and local.panel sections of the Unit 2
Alarm Book.
-
'
Mode 3 and Mode 4 Required Surveillance Check-Off Lists of OI-
3 .. 2, Cold Shutdown to Hot Standby remain to be issued.
The Fire Fighting and Organization Manual has been issued; how-
ever~ the manual does not appear to adequately cover Unit 2 in
the, following areas:
(1)
(2)
(3}
(4)
(5)
Certain new zones and fire detectors for Unit 2 have not
been added to Appendix 8 in order to perform Surveillances
4.3.3.6.1 and 4.3.3.6.*2,
Surveillance 4.7.10.1.lf(3), which requires cycling of
fire. protections system valves every 18 months, has not been
included,
C~rtain Unit 2 valves have not been included in Appendices E
and Fin order to completely accomplish Surveillances 4.7.10.4
a, b and c for* Unit 2.
Inspection of* Unit 2 fire barriers has not been included in
Appendix Jin order to accomplish Surveillance 4.7.11.a.
Appendix H requires revision to ensure proper system pressures
as specified in Surveillance 4~7.10.1.f.2 and~ are used
when testing the flow capacity of the fire pumps.
Thirty six procedures were identified as needing to be issued for
core load, of these, the following procedures remain to be issued.
II - 1.3.5, RC Leak Detection
II - 9.3.1, Manipulation Crane;
II - 9.3.2, Fuel Transfer System;
II - 9.3.3, Control Rod Shaft Unlatching Tool;
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8
II
9.3.5, Thimble Plug Handling Tool;
II - 9.4.1, Fuel Transfer System;
II - 8.3.3, Filling the Reactor Refueling Cavity;
II -* 8. 3. 4, Draining the Reactor Refueling Cavity;
II - 14.3.1, Containment Drains System Op~ratian;
II - 15.3.1, Hyctragen Recombiner - Normal Operation;
II - 15.3.2, Personnel Locks and Containment Entry;
IV - 6.3.2, Operation of the Axial Flux Deviation System
3~
Purpose of Inspection
/
To confirm that facility procedures are* prepared to adequately control
safety related operations within applicable regulatory requirements.
4.
Facility Procedure Format and Content
a.
The inspectors reviewed the below listed procedures on a sampling
basis to verify. the fa 11 owing:
. Technical content was adequate to assure satisfactory performance
of intended functions.
Format was in accordance with ANSI Nl8.7 and the licensee 1s
~dministrative co~trols.
b.
The following procedures were reviewed:
Alarm Procedures
--
- A-5, Fire Protection System Loss of 28 Volt D.C., Revision 0,
March 22, 1979.
A-6, Computer Failure, Revision 0, March 22, 1979.
A~l2, 2B Vital Instrumentation Bus Inverter Failure Fuse Blown,
Revision 0, March 22, 1979.
-e
9
A-31, 125 VDC Control Bus lB Low Voltage, Revision 0, March 22, 1979.
A-40, Solid State Protective System Train
11A11 Trouble, Revision
0, March 22, 1979 .
. --
B-2, Reactor Protection Channel I on Test, Revision 0,
March 22, 1979.
B-14) Service Water Header 21 Low Pressure, Revision 0, March 22,*
1979.
B*24, Service Water No. 21, No. 22, and No. 23 Pump Room Hi/Lo
Temperature, Revision 0, March 22, 1979.
B-38, Service. Water Screenwash No. 21, No. 22, and No. 23 Trouble,
Revision 0, Mar~h 22, 1979.
B-40, Component Cooling Heat Exchanger 21 Service Water Low Flow,
Revision 0, March 22, 1979.
C-3, Containment Pressure Hi - Hi Alarm, Revision 0, March 22,
1979.
C-13, Reactor Coolant Pump 22 Bearing Cooling Water Low Flow,
Revision 0, March 22, 1979.
C-14, Reactor Coolant Pump 22 Radial Bearing Oil Hi/Lo Level,
Revision 0, March 22, 1979.
C-19, Containment Spray Actuation, Revision 0, March 22,
1979.
C-27, Containment Isolation Phase
11A
11 Actuation, Revision 0,
March 22, 1979.
C-32, Boric Acid Batching Tank Hi/Lo Temperature, Revision 0,
March 22, * 1979.
C-38, Reactor Coolant Pump Thermal Barrier Header High Tempera-
ture, Revision 0, March 22, 1979.
D-4, Boron Injection Tank Hi/Lo Temperature, Revision 0, March 30,
1979.
D-6, Intermediate Range Loss of Detector Voltage, .Revision 0,
March 30, 1979 .
10
D-8, Rod Insertion.Low Limit, Revision 0, March 30, 1979 .
. D-20, Boron Injection Tank Low Recirculation Flow, Revision 0,
March 30, 1979.
D-30, Intermediate Range High Flux Rod Withdrawal Stop, Revision
0, March 30, 1979.
D-36, Refueling Water* Storage Tank Low Level, Revision 0, March 30,
1979.
D-38, Power Range Hi Neutron Flux Rate, Revision 0, March 30,
1979.
E:..T, SteamGenerator 21 Steam Line Isolation, Revision 0, March 30,
1979.
E-10,. Valve 2~J69 Off Normai Position (Suction Valve to .RHR
System from RWST), Revision 0, March 30, 1979.
E-20, Pressurizer Low Level Coincident, Revision 0, March 30,
1979 ..
E~35, Reactor Coolant Pumps No. 21, No. 22, No. 23, and No. 24 Hi
Vibration, Revision 0, March 30, 1979.
E-37, Low Tavg and Reactor Trip 2/2, Revision 0, March 30, 1979.
E-13", RC Loop 22 Low Fl ow or RCP 22. Breaker Open 1/ 4, Revis ion 0,
March 30, 1979.
Operations Department Survei 11 ance Procedures
SP(O) 4.1.2.l(b), Reactiv*ity Control System - Boration, Revision
0, March 22, 1979
SP(O) 4.3.4.l.2(a), Turbine Overspeed Protection, Revision 0,
April 9, 1979.
SP(O) 4.6.2.2(d), Containment System - Spray Additive, Revision
0, March 7, 1979.
SP(O) 4.6.2.3(a), Containment Systems - Cooling System, Revision
0, March 22, 1979~
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11
SP(O) 4.7.1.2(a), Plant Systems - Auxiliary Feedwater, Revision
0, March 26, 1979.
SP(O) 4.7.6.l(a), Plant Systems - Control Room Ventilation,
Revision 0, March 22, 1979.
SP(O) 4. 6. 2. 2(d), Containment Systems - Spray A_dditive, Unit No.
- 2, Revision 0, March 7, 1979.
SP(O.) 4.3.2.1.3, Engineered Safety Feature Response Time Testing,
Unit. No. 2, Revision 0, March 1, 1979.
SP(O) 4~3.1. Ll, Instrumentation - Reactor Trip System - Reactor
Trip Breaker~ Uhit No~ 2, Revision 0, March 22, 1979.
SP(O) 4.3.2.l.l(d), Engineered Safety Feature -
Steam Line
Isolation, Unit No. 2, Revision 0, March 22, 1979.
SP(O) 4.3.3.5, Instrumentation - Remote Shutdown Station, Unit
_No. 2, Revision 0, March 7, 1979.
SP(O) 4.5.2(b), Emergency Core Cooling - ECCS Subsystems, Unit
No .. 2, Revision 0, March 22, 1979.
SP(O) 4.5.4.1, Emergency Core Cooling - Boron Injection Tank,
Unit No. 2, Revision 0, March 22, 1979.
Maintenance Department Procedures
M3B, Safeguards Equipment Control (SEC) Sequencer Surveillance
Test, Revision 6, October 10, 1978.
M3D, 4KV and 13KV ACB Inspection and Test, Revision 4, March 2,
1979.
.
M3E, Battery Charger Test, Revision 3, March 1, 1979 .
. M3J, 4KV and 13KV Breaker Timing, Revision 3, December 12, 1978.
M3L, Motor Operated Valve Testing, Revision 7, March 1, 1979.
M9C, Steam Generator Tube Repairs, Revision 2, January 16, 1979.
MllA, Use of Freeze Seals on Stainless Steel Pipe, Revision 3,
January 29, 1979.
/
.-1
12
M16D, Containment Sump Level Alarm and Indicator Test,
M17, Maintenance Department In-Service Inspection Program, Revision
4, March 1, 1979.
Ml7D, Pump Inservice Tests, Revision 3, March 1, 1979.
M8E, Reactor Vessel Irradiated Specimen Removal, Shipping and
Testing, Revision 5, March 1, 1979.
M5F, Pressurizer Safety Valve Testing, Revision 4, February 2,
1979.
MSD, Pressurizer Safety Relief Valve Repair and Inspection,
Revision 6, March 1, 1979.
MSB, Pressurizer Inspection and Manway Gasket Replacement, Re-
vision 5, March 9, 1979.
MSA, Spray Valve Repair, Revision 6, March 1, 1979.
M3M, Periodic Battery Inspection, Revision 12, March 1, 1979.
M30, Megger Calibration, Revision 4, January 29, 1979.
M3S,
G~neral Instructions for Motor Disassembly and Reassembly,
Revision 2, March 1, 1979.
M3Y, Repair of Fire Barrier and Flood Protector Seals, Revision
2, March 1, 1979.
M3A, Battery Test Discharge, Revision 10, March I, 1979.
M8F, Control Rod Drive Mechanism Removal and Replacement; Re-
vision 2, March 1, 1979.
Procedure Number 1005, Wyle Laboratories Procedure -
Spring
Operated Safety Relief Valves, March 7, 1979.
Performance Department Surveillance Procedures
2PD-2.2.005, No. 22 Reactor Coolant Loop
T/Tavg Protection
Channel Calibration Check - Channel II, Revision 1, July 31,
1978 .
13
2PD-2.6.042, No. 22 Steam Generator Steam Pressure Protection
Channel Functional Test - Channel II, Revision 0, November 3,
1978.
.
,
2PD-2.6.039, No. _22 Steam Generator Flow Protection Channel
Functional Test- Channel II, Revision 0, November 1, 1978.
2PD-2.2.069, Containment Pressure Protection Chan~el Calibration
Check ~Channel I, Revision 0, November. 22,
1978.
2po*-*2. 5. 06T, Containment Pressure Protection Channel- Sensor
Calibratirin - Charynel *III, Revision 0, October 31,
1978.
2PD-2.2.066, Containment Pressure Protection Channel Calibration
Check-' Channel IV, Revision 0, November 22,
1978.
2PD-2.6~068, Containmeni Pressure Protection Channel Functional
Test -**Channel II,. Revision 0, November 2~ 1978.
2PD-2. 5. 065 ,. No. 24 Steam Generator Level Protecti.on -
Channel
II, Revision 0, October 31, 1978.
2PD-2.2.069, Engineered Safety Feature Actuation System Instru-
mentation Channel Calibration Check, Revision 0, June 30, 1977.
2PD-2.5.068, Engineered Safety Feature Actuation System Instrumen-
tat.ion Channel Sensor Calibration, Revision 0, October 31, 1978.
2PD-2.6.067, Containment Pressure Protection Channel Functional
Test, Revision 0, November 6, 1978.
2PD-2.6.022, Pressurizer Level. Protection Channel Functional
Test - Channel III, Revision 0, November 3, 1978.
2PD-2.2.052, No. 23 Steam Generator Steam Pressure Protection
Chan*nel Calibration Check - Channel III, Revision 1, June 6,
1978.
2PD-2.5.061, No. 24 Steam Generator Steam Pressure Protection
Channel II, Revision 0, October 31, 1978.
2PD-2.2.024, First Stage Turbine Impulse Pressure Channel Calibra-
tion Check, Revision 2, February 16, 1979 .
14
2PD-2.6.051, No. 23 Steam Generator Steam Pressure Protection,
Revi~ion 0, November 27, 1978.
I
2PD-2.7.001, Reactor Coolant Loop
T/Tavg Protection - Channel
I> Revision 0, January 31, 1978.
2PD-2:8~018, Pres~urizer Pressure Protection Channel Sensor Time
Response Test - Channel II, Revision 0, November 20, 1978.
2PD-2.8.001, Flow Channel Sensor Time Response Test, Revision 0,
November 7, 1978 ..
lPD-2.7.002, Reactor Coolant Flow Channel Time Response Test Loop
r - Channel I, Revision 0, October 10, 1978.
2PD-2.8.035, Steam Generator Level Protection Channel Sensor Time
Response Test - Channel II,' Revision 0, November 17,1978.
2PD-2. 7.035, Steam Generator Level Protection Channel Time. Re-
$ponse Test - Channel II, Revision 0, October 26,
1978.
2PD-18.4.002, Solid State Protection Time Response Test, Revision
2,. November 22,. 1977.
2PD-16.3.008, Power Range N42 Channel Calibration Check, Revision
O> Octobe~ 27, 1978.
2PD~l6.2:003, Power Range Functional Test, Revision 0, October 31,
1978. '
2PD-16.2.002, Channel Functional Test Intermediate Range, Re-
vision 4, August 22, 1977.
2PD-16.2.001, Channel Functional Test Source Rang~,. Revision 2,
August 12, 1976.
2PD-16.l.001,- Channel Calibration Source Range, Revision 2,
October 5, 1977.
2PD-2.2.001, No. 21-Reactor Coolant Loop
T/Tavg Protection
Channel Calibration Check - Channel I, Revision 1, July 28, 1978.
2PD-2.2.018, Pressurizer Pressure Protection Channel Calibration
Check - Channel II, Revision 2, June 6,
1978 .
--*.
15
2PD-2.5.018, Pressurizer Pressure Protection Channel Sensor
Calibration - Channel II, Revision 1.
2PD-2.5r017; Pressurizer Pressure Protection Channel Sensor
Calibration - 2PT-455, Revision 1, April 27,
1978.
2PD-2.6.021, Pressurizer Level Protection Channel Functional
Test - Channel II, Revision 0, October 24,
1978.
2PD-2.2~002, Reactor Coolant Flow Channel Calibration Check Loop
. 1. - Channe.l I, Revision 0, June 30, 1977.
2PD-2.5.008, Reactor Coolant Flow Channel Sensor Calibration Loop
2 - Channel II, Revision O~ October 25, 1977.
2PD-2.6 .. 0ll, Reactor Coolant Flow Channel Functional Test Loop
3 - Channel II, Revision 0, October 24, 1978.
2PD-2~2.010, Reactor Coolant Flow Channel Calibration Check Loop
3 - Channel I, Revision O~ June 30, 1977.
2PD-2.5.010, Reactor Coolant Flow Channel Sensor Calibration Loop
3 - Channel I, Revision O~ October 25, 1977.
.
,
ZPD-2.2.045, No~ 22 Steam Generator Level Protection -
Channel
I, Revision 2, June 21, 1978.
2PD-Z.5.045, No. 22 Steam Generator Level Protection -
Channel
I, Revision 0, October 30, 1978.
2PD-2.2.028, Steam Generator Flow Protection -
Channel I, Re-
vision 1, March 21, 1978.
2PD-2.2.030, No. 21 Steam Generator Steam Pressure Protection
Channel Calibration Check, Revision 0, June 30, 1977.
2PD-2.2.034, No. 21 Steam Generator Level Protection Channel
Calibration Check, Revision 0, June 30, 1977.
2PD-2.2.-004, Reactor Coolant Flow Channel Calibration Check, Loop
1 - Channel III, Revision 0, November 11, 1978.
2PD-2.2.008, Reactor Coolant Flow Channel Calibration Check, Loop
2 - Channel III, Revision 0, November 22,
1978 .
- ---
16
2PD-2.2.012, Reactor Coolant Flow Channel Calibration Check, Loop
3 - Channel III, Revision 0, November 22,
1978.
2PD-*2~2.016, Reactor Coolant Flow Channel Calibration Check, Loop
4 - Channel III, Revision 0, November 22,
1978.
2PD-18.1. 002, Sol id State Protection System Interface Cabinet,
Revision 0, February 16, 1979;
2PD-16. 2. 003 ,. Power Range Functional Test, Revision 0, October 31,
1978.'
2PD-16~5.001, Reactor Trip System Channel Time Response Test,
Revision 0,. February 16, 1979.
1(2)PD-14*. 3. 002, Instrument Response Time Test - Master, Revision.
0, January 5, 1979.
2PD-2.6.045, No~ 22 Steam Generator Level Protection Channel
Functional Test, Revision 0, October 18, 1978.
2PD-2.8.067, Containment Protection Channel Sensor Time Res~onse
Test, Revision 0, November 8, 1978.
2PD-l.4.001, NSSS'General Loop Calibration Procedure, Revision 1,
November 30, 1975.
PD-l.4~003, General Instrument Calibration Procedure for Field
Devices - ICPG-1, Revision 3, October 3, 1975.
Performance Department Manual, Revision 9, March 26, 1979.
c.
As a result of the above review, the following items were identified:
R~visions to technical specifications had not been promptly
placed in the site proof and review copies of proposed Technical
Specifications.
The Operations Department copy of Technical
Specifications, from which, it was sfated, procedures are rou-
tinely prepared and/or reviewed was noted on April 9, _1979 as not
containing the previous four Technical Specification changes
issued.
In addition, one procedure (SP(o) 4.3.4.l.2(a)). SORC
approved on April 9, 1979 was noted as not having incorporated in
it a Technical Specification change which was issued on March .
15, 1979.
17'
Procedure SP(o) 4.3.2.1.3, approved on March 1, 1979, requires
revision to include* response time testing of the auxiliary feed
pump start which was added by a later revision of the proposed
Technical Specifications.
\\
The* applicant stated that instructions would be issued which will
specify distribution of Technical Specification changes and the
actions to be taken by personnel following receipt of revisions
to the proposed Technical Specification. This item is open
pending completion of the applicant's action as noted above and
subsequent NRC RI rev.i ew..
(311/79-23-01)
A*significant number of procedural discrepancies were noted by
the inspectors and applicant personnel that require corrective
action.
The applicant's representative stated that a memo would
be* issued to require a 11 known procedural discrepancies to be
identified as required by the Station Administrative Procedures
so that corrective action can be accomplished.
The fbllowing are
examples that were identified and require procedure changes:
(1)
Reactiv1ty Constrol System - Boration operating procedure,
valve list does not specify seal flow control valves locked*
open yet a valve surveillance procedure specifies the valves
locked open.
Changes to Unit 1 procedures are not being applied to Unit
2..
A procedure change written to lock open four seal flow
isolation valves located inside containment in procedure
SP(o) 4.1.2.l(b) for Unit 1 were not similarly changed to
locked open in the Unit 2 procedure.
(2) Alarm procedure E-7 states in part, a set point for low
- steam pressure of 600 psig or T average set point of less
than 540F.
These set points are not in accordance with set
points listed in T.S. Table 3.3-4 of low steam pressure
greater than 500 psig and T average of greater than 543F.
(3) Alarm procedure 8-38 for Unit 1 states a service water
strainer differential pressure set point of
11greater than 10
inches.
11
The correct setpoint for this alarm per Public
Service Drawing #203822 is
11greater than 6 inches.
11
- (4) * Alarm procedures D-20 and 0-36 have had alarm response
actions added to the procedures for Unit 2.
These addi-
tional actions a~e also pertinent to Unit 1 ~larm procedures
D-20 and D-36; however, these procedures have not yet been
revised for Unit 1.
-1
. '
- 18
(5) Alarm procedures B-14 and E-7 appear to reference incorrect
Technical Specifications concerning supplemental actions.
This item is open pending applicant action as-noted above
and subsequent NRC RI review (311/79-23,..02).
During* review of the Maintenance Department Manual (MOM), several
occasions were noted where copies of the MOM did not appear to
.have.been properly controlled.
This apparent item of noncompli-
anca (Unit. 1) will be addressed in inspection report 50-27i/79-
- i'2.~
- ".': . .
.
~
5.
Calibration - Safety Related Components Not Identified* In Technical
Speci fi cations
a.
The: inspector performed a program review to *verify the following:
b.
Calibration requirements have been established including frequency,
department responsibilities, and calibration status;
responsibility assigned to maintain the master calibration schedule
current; *
requirements established to perform component ~alibrations with
approved procedures.
The* foll_owi ng safety -related components were selected to verify that:
The instruments have been included in a master calibration program;
calibration procedures have been prepared and approved~
Proposed Technical
Specification
3.5.1.d
3.5.1.b
3.7.10.3.b
3.7.1.3
4. 7 .1. 2
Description*
Accumulator nitrogen cover pressure
Accumulator volume
Diesel fuel oil storage tank level
and pressure
Auxiliary feed storage tank level
Auxiliary feed pump discharge pressure
No open items were identified.
--1
........ ,,
f .. .,,
19
6.
Open * Items
Open items are findings associated with documents/procedures that the
applicant intends to use to implement regulatory requirements upon receipt
of the operating license.
Open items disclosed during the inspection are
discussed in paragraph 4.
7.
Exit Interview
The inspectors met with applicant's representatives (denoted in paragraph
}.) at the conclusion of the inspection on.,April 12 ~ _l 979. __ Th~ __ sc_op_e~ an_~-----_
findings of the inspection were discussed. - - --