ML20216C874
| ML20216C874 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 04/08/1998 |
| From: | Mendonca M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216C870 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9804150086 | |
| Download: ML20216C874 (76) | |
Text
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4 UNITED STATES g
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055!M001
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PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-133 l
HUMBOLDT BAY POWER PLANT, UNIT 3 i
AMENDMENT TO FACILITY LICENSE l
t Amendment No. 32 License No. DPR-7 l
1.
The U.S. Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment by Pacific Gas and Electric Company (the licensee) dated December 9,1996, as supplemented on June 12,1997 and March 13,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as set forth in 10 CFR Chapter I; I
j B.
The facility will be maintained in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; 1
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the regulations of the Commission; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the regulations of the Commission and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of Facility License No. DPR 2 is hereby amended to read as follows:
9804150086 980400 1
PDR ADOCK 05000133 p
4 2
(2) Technical Specifications The Technical Soecifications contained in Appendix A, as revised through Amendment No. 32, are hereby incorporated in the license. Pacific Gas and electric company shall maintain the facility in accordance with the Technical Specifications.
1 3.
This license amendment is effective as of the date of its issuance and shall be implemented no later than 30 days from the date of issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION
- w c!n. -
Marvin M. Mendonca, Ar,o a Director l
Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation
Enclosure:
Changes to the Technical Specifications Date of issuance: - April 8,1998 i
l-1
4 ATTACHMENT TO LICENSE AMENDMENT NO. 32 FACILITY LICENSE NO. DPR-7 DOCKET NO. 50-133 The Appendix A Technical Specifications have been revised to implement Generic Letter 89-01 and to incorporate the requirements of the most recent revision to 10 CFR Part 20 and Appendix l to 10 CFR Part 50.
l Apga-.x A is also being republished in its entirety with the issuance of this license amendment.
This is a clerical action to permit the use of upgraded word processing technology to support future maintenance of the document. Therefore, Appendix A is to be replaced in its entirety with the Appendix A issued by this license amendment. To ensure continuity between the previous and new Technical Specifications, a complete list of effective pages is provided below.
I PAGE AMEMDMENT Cover Sheet Not applicable i thru iv 32 J
1-1 31 1-2 thru l-4 32, 11-1 30 11-2 See Note ll-3 30 111-1 thru 111-2 See Note 111-3 31 lll-4 thru 111-5 See Note IV-1 thru IV-4 See Note IV-5 thru IV-6 31 IV-7 See Note IV-8 31 IV-9 thru IV-11 See Note V-1 thru V-4 32 V-5 31 V-6 thru V-9 32 VI-1 thru VI-2 32 Vil-1 24 i
Vll-2 31 Vll-3 See Note l
Vll-4 thru Vll-6 31 1
Vll-7 28 Vll-8 thru Vll-9 31 Vil-10 See Note Vil-11 31 j
Vll-12 See Note Vil-13 31 j
I 2
l PAGE (continued)
AMENDMENT l
Vll-14 thru Vll-19 25 Vil-20 thru Vll-27 32 Vil-28 See Note l
Vll-29 thru Vil-33 32 l
NOTE: Amendment No. 23, issued on July 19,1988, included, among other things, an initial issuance of a complete set of new Technical Specifications (Appendix A) to support the possess-but-not-operate status of the plant. Alicense amendment number did not appear on the new pages issued with Amendment 23, and some of those pages have not been modified by any subsequent license amendments. These unmodified pages, which continue to have no amendment number, are: ll-2, ill-1 thru 111-2, Ill-4 thru lll-5, IV-1 thru IV-4, IV-7, IV-9 thru IV-11, Vil-3, Vil-10, Vil-12, Vil-28.
Other pages have been mc._. sed by license amendments issued after Amendment 23, b'
and each one of those pages was annotated, as a part of that licensing action, with the most recent amendment number that revised the page.
l
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i DOCKET NO. 50-133 APPENDIX A LICENSE NO. DPR-7 TECHNICAL SPECIFICATIONS FOR HUMBOLDT BAY POWER PLANT UNIT 3
)
i CONTENTS Section
_P_gge 1.
I NTR O D U CTI O N..................................................................................... 1 -1 A.
Scope............................................................................................1-1 B.
D efi n i ti o n s..........................................................................................
1.
Administrative C ontrols......................................................... 1-2 2.
De si g n F eature s....................................................................... 1-2 3.
E l e va t i on................................................................................. 1 -2 4.
Offsite Dose Calculation Manual.............................................. 1-2 5.
Operable, Operability............................................................. 1-3 6.
O pe rating Limits....................................................................... 1-3 7.
Operating Requirements......................................................... 1-3 8.
Proce s s C ontrol Program........................................................ 1-3 9.
S AF ST O R............................................................................... l.4 10.
S pe n t F u e l............................................................................... 1 -4 11.
Stagge red Test Basis............................................................... 1-4 ll.
SITE.,......................................................................................................11-1 A.
L o ca t i o n.........................................................................................
B.
P l a n t Are a s.......................... l............................................................. I l-C.
P ri nci p al Activitie s............................................................................... 11-1 Ill.
S T R U CTU R E S............................................................................................. 111 A.
De si g n Fe at u re s.................................................................................. 111-1 1.
Refueling Building..................................................................... il l.1 2.
Spent Fuel Storage Pool.......................................................... lll-1 B.
Operating Limits and Requirements.................................................... lli-2 1.
Refueling B uilding..................................................................... Ill-2 2.
S pent F uel Storage Pool........................................................... lli-2 l
3.
Neutron Absorber Surveillance Program....................'............... lll-3 IV.
S E RVI C E SY STE M S...................................................................................... IV-1 A.
De si g n Fe at u re s................................................................................... IV-1 1.
Refueling Building Ventilation System...................................... lV-1 2.
Spent Fuel Storage Pool Service System................................. IV-1 3.
Fire Protection System............................................................. IV-2 4.
E lectrical Systems.................................................................... IV-3 B.
Operating Limits and Requirements..................................................... IV-3 1
1.
Refueling Building Ventilation System...................................... IV-3 2.
Spent Fuel Storage Pool Service System................................. IV-4 3.
Fire P rotection S ystem '.............................................................. IV.4 i
Amendment No. 32
Section Pace 4
Fire H ose S tation s............................................................... IV-8 5.
Penetration Fire Barriers.............................................. IV-9 6.
Ele ctrical S y ste ms............................................................... IV-9 V.
M O N IT O R I N G S Y S TE M S............................................................................ V-1 A.
D e si g n f e at u re s............................................................................. V-1 1.
Deleted 2.
Deleted 3.
Area Monitors and Portable Monitoring Equipment.................V-1 1
4.
Deleted 5.
Spent Fuel Storage Pool Water Level Monitors......................V-2 6.
Deleted B.
Operating Limits and Requirements..................................................V-2 1.
Deleted 2.
Deleted
]
3.
Area Monitors and Portable Monitoring Equipment...................V-2 4.
Deleted 5.
Spent Fuel Storage Pool Water Level Monitors......................V-4 6.
Deleted 1
7.
Se aled Source Leak Testing.................................................. V-4 VI.
WASTE D I S P O S AL SYSTEM S................................................................... VI-1 A.
Deleted 1.
Deleted 2.
Deleted 8.
Operating Limits and Requirements...................................................VI-1 1.
Liquid Radioactive Waste System...........................................VI-1 2.
Solid Radioactive Waste System............................................VI-1
)
3.
Deleted Vll.
AD MI N I STRATIVE C O NTRO LS.................................................................... Vll-1 A.
R e s p on s i bility...................................................................................... Vi l-1 B.
O rg a n izati on...................................................................................... Vi l-1 C.
P l a nt S t aff.................................................................................... Vi l-2 1.
Requirements for the Shift Operating Organization..................Vil-2 2.
Plant Staff Q ualifications.......................................................... Vil-3 3.
Fire Protection Program.......................................................... Vil-7 4.
Tra i n i n g................................................................................ Vi l-8 ii Amendment No. 32 l
Section Eage D.
R e view a n d Au d it........................................................................... Vi l-10 1.
Plant Staff Review Committee........................................
..... Vil-10 2.
Nuclear Safety Oversight Committee..................................Vil-14 E.
P ro ce d u re s.....................................................................................
1.
Detailed Proced u res................................................................. Vl l-19 2
Procedure Review................................................................... Vi l-20 3.
Proced ure C hanges.................................................................. Vi l-21 i -
4.
Emergencies Not Covered by a Procedure...............................Vil-21 l
F.
Radioactive Effluent Controls Program..........................................Vll-21 l
G.
Radiological Environmental Monitoring Program...............................Vil-24 l
l H.
S ite Eme rg en cy Plan........................................................................ Vl l-24 l
1.
S u rveilla n ce Te sting....................................................................... Vil-2 5 J.
R epo rtin g Req uireme nts............................................................. Vil-25 1.
An n u al R e p o rt......................................................................... Vl l-2 5 2.
N onroutine Re ports.................................................................. Vi l-26 3.
An n u a l Effl u e nt R e le a s e R eport................................................ Vi l-26 4.
S pe ci a l R e po rt s..................................................................... Vi l-27 K.
Re co rd-R e tenti on........................................................................... 3 1.
Five-Year R etention.............................................................. Vil-2 7 2.
S AF STO R D uration............................................................... Vll-28 L.
Ra diation Prote ction Program............................................................. Vil-29 M.
High R a diation Area........................................................................ Vi l-30 1.
Less Than or Equal to 1000 mrom/hr........................................Vil-30 2.
Greater Than 1000 mrem /hr...................................................... Vil-31 N.
Process Control Pre Am Changes....................................................Vll-31 O.
Offsite Dose Cs!!:ulation Manual Changes.........................................Vil-32 I
i i
iii Amendment No. 32 1
1 4
TABLES IBM.!!
Ea2R lil-1 Refueling Building Penetrations for Personnel and ll14 Equipment Entry, and for Ventilation Systems 111-2 Limits for Spent Fuel Storage Pool Water Chemistry and 111-5 Activity During SAFSTOR IV Fire Hose Stations IV-11 V Deleted FIGURES Einwra Eaat i
11-1 Unrestricted Area ll-2 ll-2 Deleted i
V-1 Deleted -
l V-2 Deleted j
l V-3 Deleted j
l 1
i iv Amendment No. 32 i
i
1.
INTRODUCTION A.
SCOPE These Technical Specifications set forth the principal DES GN FEATURES and OPERATING LIMITS AND REQUIREMENTS for Unit 3 (the Unit) at Pacific Gas and Electric Company's (the Company's) Humboldt Bay Pow; - Plant (the Plant or HBPP).
The Unit originally operated as a nuclear power plant with a single-cycle, natural circulation, boiling water reactor and associated turbine generator. As part of the decommissioning of the Unit, most systems have been removed from service. Systems still in operation are used for the storage of spent reactor fuel, the monitoring and surveillance of the Unit during SAFSTOR and the processing of radioactive wastes generated during SAFSTOR. Systems and components
- that have been removed from service are not described in these Technical Specifications.
l Section 11 of these Technical Specifications describes the site. Sections til through VI describe structures, systems, and components used during SAFSTOR and specify the conditions under which they shall be controlled and monitored. Each of Sections ill through VI consists of:
A description of significant DESIGN FEATURES. Where thermal, e
hydraulic, and nuclear characteristics of various systems are given, they are subject to normal manufacturing tolerances unless specific tolerances are stated.
1-1 Amendment No. 31
A list of the O' MATING LIMITS AND REQUIREMENTS. Whenever a condition occurs that requires corrective action to ensure operation or maintenance within these limits and requirements, such action shall be taken in a timely manner.
l Section Vil of these Technical Specifications covers administrative and l
procedural requirements, including the review of proposed changes in DESIGN FEATURES, OPERATING LIMITS AND REQUIREMENTS, and procedures, it s',o requires procedures for normal and emergency conditions during SAFSTOR.
l I
B.
DEFINITl_ONS l
~
1.
ADMINISTRATIVE CONTROLS: The provisions relating to the organization, management, procedures, record keeping, reviews and audits, and reporting that are necessary to ensure maintenance of the Plant in a safe condition during SAFSTOR.
2.
DESIGN FEATURES: Those features of the Plant which, if altered or modified, could have a significant effect on the ability of a system, component, or structure to perform its intended function.
3.
ELEVATION: All elevations shall apply to a datum of mean lower low water (MLLW) level except where noted.
4.
OFFSITE DOSE CALCULATION MANUAL: The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the methodobgy and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environment Monitoring Program.
1-2 Amendment No. 32
1 i
The ODCM also contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section Vll.F, and (2) descriptions of the information that should be included in the Annual SAFSTOR Radiological Environmental Monitoring and Annual Effluent Release Reports required by Specifications Vll.J.1 and Vll.J.3.
5.
OPERABLE, OPERABILITY: A system, subsystem, train, component, or device may be considered OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electric power sources, cooling or seal water, lubrication, or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s)
I are also capable of performing their related support function (s).
6.
OPERATING LIMITS: The lowest functional capability, performance levels, or safety limits of structures, systems, or components required during SAFSTOR.
7.
OPERATING REQUIREMENTS: Those requirements relating to operation, test, calibration, surveillance, or inspection to ensure that operating limits will be met.
8.
PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM (PCP) contains the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements goveming the disposal of solid radioactive waste.
I-3 Amendment No. 32
1 9.
3AFSTOR: The period of time during which the Unit is maintained in a condition of monitored protective storage until the final decommissioning of the Unit.
10.
SPENT FUEL: Nuclear fuel that has been removed from the reactor vessel after having been used in critical power generation.
11.
STAGGERED TEST BASIS: (a) A test schedule for n (where n is equal to a number) systems, subsystems, trains, or other designated components l
obtained by dividing the specified test interval into n equal subintervals, and (b) the testing of one system, subsystern, train, or other designated component at the beginning of each subinterval.
i l
l l
t I-4 Amendment No. 32
II.
SITE A.
LOCATION The Unit is located in Humboldt County, California, approximately 4 miles southwest of the center of the city of Eureka, on a site owned and controlled by the Company.
B.
PLANT AREAS The unrestricted area used in the offsite dose calculations for gaseous and liquid effluent is shown in Figure 11-1. Ingress and egress are controlled by the Company.
The restricted area shall be defined in plant procedures.
C.
PRINCIPAL ACTIVITIES The principal activities of the Plant are those related to the generation and transmission of electric power and the associated service activities. Activities associated with the Unit consist of storage and surveillance of SPENT FUEL, monitoring and surveillance of the decommissioned facility, and operations and maintenance to support the above-mentioned activities in accordance with Regulatory Guide 1.86, Section C.S.
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11 - 1 Amendment No. 30 l
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Amendment No. 30 l
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1 lil.
STRUCTURES The refueling building and the spent fuel storm ' pool will contain the SPENT FUEL during SAFSTOR. This section describes the
N FEATURES and OPERATING LIMITS AND REQUIREMENTS that will continue th.vugh SAFSTOR.
A.
DESIGN FEATURES i
4 1.
Refuelina Buildino I
The refueling building is a reinforced concrete structure located immediately above the reactor caisson. The spent fuel storage pool is located in the refueling building.
The building functions as a weather enclosure, contamination control barrier, and radiation shield.
Refueling building penetrations for personnel and equipment entry and for ventilation systems are described in Table lll-1.
1 2.
Spent Fuel Storace Pool j
The spent fuel storage pool is a reinforced concrete structure integral to the reactor caisson. It is 26 feet deep except for a cask loading pit in one corner, wtiich is 36 feet deep. The water in the pool provides shielding and contaminatior ".antrol. A stainless steel liner shall comple;ely cover 111 - 1
the inside surfaces of the spent fuel storage pool with a nominal gap of 1/4 inch between the liner and the walls and the floor.
Each spent fuel assembly except assembly UD-6N shall be stored in containers made of neutron absorbing material if the spent fuel racks were to fail, the containers would prevent criticality.
A cover shall normally be installed over the spent fuel storage pool to l
prevent objects from falling into the pool and to serve as a contamination control barrier.
B.
OPERATING LIMITS AND REQUIREMENTS 1.
Refuelino Buildino A thorough visual inspection of the refueling building shall be conducted at least quarterly. Evidence of deterioration shall be evaluated with l
regard to the function of the building as a weather enclosure, contamination control barrier, and radiation shield.
l 2.
Spent Fuel Storace Pool a.
Water Level - Pool water level shall be maintained at an ELEVATION greater than 10.5 feet (within 1.5 feet below the main floor of the refueling building). The water level between the liner and the concrete walls shall be maintained below ELEVATION +9 t-Inches (11.25 feet or greater below the main floor of the refueling building). The main floor of the refueling building is at ELEVATION
+12 feet.
lll - 2
)
I l
b.
Water Quality - Water quality in the spent fuel storage pool shall j
be maintained within the limits specified in Table 111-2. Spent fuel storage peol water shall be sampled and analyzed at least once per month. wa;9r quality limits are exceeded, action shall be l
taken to restore the water quality to within limits and an evaluation i
shall be conducted to determine the cause, if water quality cannot j
be restored within the limits specified before the next required sampling, a report shall be submitted to the Regional l
Administrator, NRC Region IV, within the following 30 days.
l I
3.
Neutron Absorber Surveillance Proaram l
l Samples of the neutron-absorbing material used to fabricate the spent l
fuel assembly containers shallte suspended in the spent fuel storage pool in the vicinity of the spent fuel assemblies. A program shall be established to remove representative samples at specified intervals for examination and analysis to verify that the Boron-10 loading is greater 4
than 0.005 grams per square centimeter.
Ill - 3 '
Amendment No. 31
6 0
t TABLE 111-1 l-l REFUELING BUILDING PENETRATIONS FOR PERSONNEL AND EQUIPMENT ENTRY AND FOR VENTILATION SYSTEMS l
No.
Size Type of Closure Railroad door entry 1
15 ft x 16 ft Normally locked entry Personnel air locks 2
25-1/2 in. x Two mechanically interlocked 66 in.
doors in series i
Caisson personnel 1
3 ft dia Hatch and doors in series")
emergency exit shaft Main ventilation 1
16 in. dia One 16-in. air-operated isolation valve system supply duct Main ventilation 2
16 in. dia Two 16-in. air-operated system exhaust ducts isolation valves (*)
Dry well purge 1
14 in, dia Two 8-in. air-operated system exhaust duct isolation valves (a)
In addition to the ventilation system penetrations listed above, two ducts associated with the gas treatment system are considered building penetrations.
Valves in the ducts shall normally be closed, but shall be opened when the refueling building ventilation exhaust is through the gas treatment system.
(b)
Hatch is locked and cannot be opened from outside the exit shaft except with key.
The lock will not prevent emergency exit from the caisson.
(c)
Two 16-inch exhaust ducts from the refueling building join together to form a i
single duct. The two isolation valves are in series in this duct.
Ill - 4
!t
l TABLE 111-2 LIMITS FOR SPENT FUEL STORAGE POOL WATER CHEMISTRY l
AND ACTIVITY DURING SAFSTOR l
1 Parameter Limits" l
i 1.
pH 5.3 to 6.5 j
2.
- 0.5 ppm (maximum) 3.
Conductivity 10.0 mho/cm (maximum) 4.
Cs-137 activity")
1.0 x 10" Ci/ml (maximum)
-(a)
Verification shall be accomplished by analysis of samples taken at least once each month.
l (b)
Chloride analysis is required only if conductivity exceeds 2.0 mho/cm (Reference NRC Regulatory Guide 1.56, Figure 2).
(c)
By gamma spectrometry.
i Ill - 5 i
I IV.
SERVICE SYSTEMS l
[
j The refueling building ventilation system, the spent fuel pool service system, the fire protection system, and several electrical systems provide services that maintain habitability and safe conditions within the Plant during SAFSTOR. This section describes the DESIGN FEATURES and the OPERATING LIMITS AND REQUIREMENTS that are important to the continued operation of these systems.
A.
DESIGN FEATURES 1.
Refuelina Buildina Ventilation System The refueling building ventilation system shall provide normal ventilation to the refueling building. The system shall exhaust to the main ventilation exhaust stack. Isolation valves shall be provided to permit isolation of the refueling building.
2.
Spent Fuel Storace Pool Gervice System L
Makeup water for the spent fuel storage pool shall be provided from the domineralized water system. The capacity of the domineralized water tank shall be 5,000 gallons. Water to the domineralized water tank shall normally be supplied from the Units 1 and 2 condensate storage tanks.
Emergency makeup water to the spent fuel storage pool shall be available from the plant fire system.
Spent fuel storage pool water quality shall be maintained by circulation of pool water through a domineralizer by either of two spent fuel pool
(
circulating water pumps.
I IV - 1
I Water level in the gap between the spent fuel pool liner and the concrete wall shall be maintained by using a liner gap pump, which discharges to the liquid radioactive waste collection system.
a 3.
Fire Protection System j
The fire protection system consists of the fire water system, fire hose stations, and penetration fire barriers:
I a.
The fire water system shall consist of three plant fire pumps each rated for 500 gpm at a discharge pressure of 120 psig. These pumps shall take suction from the 300,000-gallon raw water storage tank. The raw water storage tank shall have a low level alarm set at 200,000 gallons. Two of these pumps shall be powered from separate Unit 1 and 2 480 volt ac systems. The third pump shall be diesel powered. The pumps shall start automatically to maintain system pressure.
i b.
Fire hose stations in the Unit shall consist of those stations and
)
equipment listed in Table IV-1.
c.
Penetration fire barriers shall be provided for penetrations between the control room and the feed pump room, between the feed pump room and the refueling building, and between the control room and the refueling building. Penetration fire barriers shall be passive devices that ensure that a fire will be confined or adequately l
retarded from spreading to other portions of the facility.
l IV-2 l
l 4.
Electrical Systems l
Switchgear shall be provided so that the Unit's electrical equipment can l
receive power from any one of three independent power sources:
l l
Unit 1, Unit 2, or the Plant 60 kV bus.
I B.
OPERATING LIMITS AND REQUIREMENTS 1
1.
Refuelina Paildino Ventilation System l
l The refueling building ventilation system shall be operated to maintain a negative pressure of at least 1/4 inch of water whenever SPENT FUEL is being moved or whenever work that might potentially damage SPENT FUEL assemblies is in progress.
b.
The capability of the refueling building ventilation system to a
maintain a negative pressure of 1/4 inch of water in the refueling building shall be tested at the following times:
(1)
Before removal of the SPENT FUEL pool cover l
(2)
After any opening of the railroad door (Penetration #1) i (3)
After maintenance that may have affected any of the j
refueling building penetration closure seals.
If not required for these reasons, the test shall be performed at least once each quarter.
IV - 3
l 2.
Spent Fuel Storace Pool Service Systems
(
a.
A minimum of 2,000 gallons shall be maintained in the demineralized water tank.
l l
b.
At least once per 31 days, the operability of the spent fuel storage l
pool liner gap pump shall be verified.
3.
Fire Protection System a.
The fire protection system shall be OPERABLE with:
4 (1)
Two plant fire pumps, each with a rated capacity of 500 gpm, with their discharge aligned to the fire suppression header.
(2)
A minimum of 200,000 gallons in the raw water storage tank.
(3)
An OPERABLE flow path capable of taking suction from the water supply tank and transferring the water through the distribution piping (with OPERABLE sectionalizing control or isolation valves) to the yard hydrant curb valves and the front valve in each hose standpipe listed in Table IV-1.
b.
If the fire water system is inoperable, the system shall be restored to OPERABLE status within 7 days or a Special Report shall be prepared and submitted to the NRC Regional Administrator for l
IV - 4 l
Region IV within 30 days outlining the compensatory measures taken and a schedule of corrective action.
c.
The following inspections and tests shall be performed:
(1)
At least once per 7 days, the raw water supply tank volume shall be verified to be at least 200,000 gallons.
(2)
At least once per 31 days, on a STAGGERED TEST BASIS, each OPERABLE pump shall be started and operated for at
]
least 15 minutes on recirculation flow.
(3)
At least once per 31 days, it shall be verified that each valve (manual, power-operated, or automatic) in the flow path is in its correct position.
(4)
At least once per 12 months, each testable valve in the flow path shall be cycled through at least one complete cycle of full travel.
(5)
At least once per 18 months:
a)
A system functional test shall be performed which includes simulated automatic actuation of the system throughout its operating sequence.
b)
Each pump shall be verified to develop at least 450 gpm flow at a total head of 240 feet.
IV - 5 Amendment No. 31
i c)
Each fire p' imp shall be v:irifi:d to start (stqu:;ntially) at a sustair,ed fire suppression water system pressure no less than 45 psig.
(6)
At least every 2 years, the raw water storage tank low level l
alarm shall be calibrated to 200,000 gallons 15%.
l (7)
At least once per 3 years, flow tests of the system shall be performed in accordance with Chapter 5, Section 11, " Fire Protection Handbook," 14th edition, published by the
[
L National Fire Protection Association.
l (8)
The fire pump diesel engine shall be demonstrated l
OPERABLE as follows:
l i
(
a)
At least once per 31 days:
l l
l (i)
The fuel storage tank shall be verified to contain at least 150 gallons of fuel.
(ii)
The diesel shall be verified to start from i
ambient conditions and operate for at least 20 minutes.
(b)-
At least once per 92 days, a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, shall be verified to be within the i =
acceptable limits specified in Table 1 of ASTM D-975 -
74 with respect to viscosity, water content, and sediment.
IV - 6 Amendment No. 31 l
I C
9 (c)
At least once per 18 months, the diesel shall be verified to start from ambient conditions on the autostart signal and operate for at least 15 minutes while loaded with the fire pump.
j (d)
The diesel shall be subjected to manufacturer's l
recommended servicing.
(9)
The fire pump diesel starting 12-volt batteries and chargers I
shall be demonstrated OPERABLE as follows:
a)
At least once per 31 days:
(i)
Thi electrolyte level of each battery shall be verified to be above the plates.
(ii)
Each battery's overall voltage shall be verified to be no less than 12 volts.
l b)
At least once per 92 days, specific gravity shall be l
verified to be 1.19 or greater.
l-c)
At least once per 18 months:
l (i)
The batteries, cell plates, and battery racks shall be ve.srified to show no visual indication of physical damage or abnormal deterioration.
(ii)
The battery-to-battery and terminal connections shall be verified to be clean, tight, IV - 7 4
)
free of corrosion, and coated with anticorrosion l
material.
4.
Fire Hose Stations a.
The fire hose stations listed on Table IV-1 shall be OPERABLE l
whenever equipment in the area is required to be OPERABLE.
l b.
When a hose station required to be OPERABLE is inoperable, an additional equivalent capacity hose shall be routed to the unprotected area from an OPERABLE hose station within i hour.
c.
Each fire hose station shall be verified OPERABLE as follows:
l (1)
At least once per 31 days by visual inspection of the station l
to ensure that all equipment is available.
l (2)
At least once per 18 months by removing the hose for inspection and reracking and by replacing all gaskets in the couplings that are degraded.
(3)
At least once per 3 years by partially opening each hose l
station valve to verify valve operability and no blockage.
(4)
At least once per 3 years by conducting a hose hydrostatic l
test at a pressure at least 50 psig greater than the maximum pressure available at that hose station.
IV - 8 Amendment No. 31
r i
5.
a.
Penetration fire barriers shall be functional at all times.
b.
When a penetration fire barrier is inoperable, a continuous fire detection capability shall be established on at least one side of the affected penetration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and shall be maintained for as long as equipment on either side of the barrier is required to be l
1 c.
Penetration Fire Barriers shall be verified to be functional by a visual inspection:
~
o At least once per 18 months o
Prior to declaring a penetration fire barrier functional following repairs or maintenance 6.
Electrical Systems l
a.
The emergency section of the 480 volt ac system normally shall be supplied from one of the Unit's two 480 volt ac buses. Provision shall be made for transferring the emergency section to a 480 volt ac source from Unit 1 or 2 and subsequently to an emergency l
generator rated at 60 kW. These transfers shall be initiated l
automatically by undervoltage relays on the emergency section.
l The emergency section shall supply the following loads:
(1)
Emergency lighting IV - 9
I
(
(2)
Main annunciator system i
(3)
The following radiation monitoring systems:
stack gss e
i i
e process monitor l
area monitors l
b.
The transfer of the emergency 480 volt ac shall be tested for proper operation at least quarterly. This transfer shall be functionally tested annually with all loads connected to simulate emergency operation.
4 I
l l
IV - 10
i TABLE IV-1 l
FIRE HOSE STATIONS l
Fire Hose Station Location Size Type l
I l
West wall of the reactor feed pump 1.5 in. x 50 ft.
Hose reel spray nozzle l
room opposite the motor-generator sets Reactor feed pump room at foot of 1.5 in. x 50 ft.
Hose reel spray nozzle stairs Refueling building north wall near air 1.5 in. x 50 ft.
Hose reel spray nozzle lock Refueling building top of stairs 1.5 in. x 50 ft.
Hose reel spray nozzle i
air lock North wall of makeup demineralizer
' 5 in. x 50 ft.
Hose reel spray nozzle room East wall of control room 1.5 in. x 100 ft.
Hose reel fog nozzle I
North wall of turbine wash-down 1.5 in. x 100 ft.
Hose reel fog nozzle Roof of refueling building 1.5 in. x 100 ft.
Hose reel fog nozzle i
i IV - 11
V.
MONITORING SYSTEMS A.
DESIGN FEATURES 1.
Deleted 2.
Deleted 3.
Area Monitors and Portable Monitorina Eauipment Fixed gamma monitors with ranges of 0.01 to 100 mr/hr or 0.01 mr/hr to 10 r/hr shall be installed at various locations throughout the Unit. The outputs of these monitors shall be recorded in the control room. Each channel shall have an adjustable high radiation alarm which is annunciated.
One area monitor shall be located in each of the following locr'Ns:
o Refueling building, south wall access door o
Refueling building, northwest access door i
l A high radiation signal from either of these channels shall provide a
- Building Above Normal Radiation" signal which is annunciated in the control room. These two area monitoring channels shall also provide i
gamma monitoring of the fuel storage areas. A high radiation level signal from either of these channels shall sound the evacuation horns in the refueling building.
V-1 Amendment No. 32 4
L
in addition to the area monitoring system, suitable portable and fixed, alpha and beta-gamnu, detection instruments and beta-gamma dose rate instruments shall be provided for use of personnel entering the Unit radiation areas and radioactive materials areas and for analyzing samples.
4.
Deleted l
5.
Soent Fuel Storace Pool Water Level Monitors Two water level indicating devices shall be installed in the SPENT FUEL l
storage pool. The outputs of these monitors shall be indicated in the control room. Annunciation (visual and audible) of low water level shall be provided in the control roorn.
6.
Deleted B.
OPERATING LIMITS AND REQUIREMENTS 1.
Deleted 2.
Deleted 3.
Area Monitors and Portable Monitorino Eouloment 1
a.
The area monitors shall normally be in service at all times. They may be taken out cf service for maintenance purposes but shall be retumed to service as soon as practicable.
V-2 Amendment No. 32 4
b.
The two area monitors in the refueling building shall alarm at 15 mr/hr. At least one of these channels shall be available to monitor L
the fuel storage area and sound the evacuation homs in the refueling building. If this condition cannot be met, monitoring shall be accomplished with portable instruments whenever personnel are in the refueling building.
l l
c.
The remainder of the area monitors shall be set to alarm either at 1 mr/hr or at a radiation level within a factor of 2 of the normal maximum indicated radiation level.
d.
The calibration of area monitors shall be checked at least once each quarter. The monitors shall be source-checked at least once each month and shall be calibrated annually.
e.
Portable radiation detection instruments shall be calibrated at least
- annually,
)
f.
Fixed and portable equipment will be used to support the following survey and sampling program: A gross beta-gamma radiation survey and a contamination survey of the Plant shall be condu:ted at least quarterly to verify that no radioactive material is escap ng or being transported through evntainment barriers. Contamination samples shall be taken along the most probable path by which radioactive material (t,uch as that stored in the inner containment l
regions) could be tra1 sported to the outer regions of the Plant and ultimately to the environs.
l 4.
Deleted t
V-3 Amendment No. 32 L
5.
Spent Fuel Storace Pool Water Level Monitors At least one water level monitor shall normally be OPERABLE at all times.
One water level monitor at a time may be taken out of service for maintenance purposes but shall be returned to service as soon as practicable. At any time when both spent fuel pool water level monitors are inoperable, the water level shall be visually checked at least once each day.
The monitors shall be set to annunciate a low level condition whenever the water level in the spent fuel storage pool drops below ELEVATION 10 l
feet,8 inches. Level indication of the spent fuel storage pool water level monitors shall be verified monthly. The level monitors shall be calibrated and the alarm setpoints verified annually.
6.
Deleted l
l 7.
Sealed Source Leak Testino a.
Each sealed source containing radioactive material in excess of 100 Ci of beta-and/or gamma-emitting material or 10 pCi of alpha-I emitting material shall be tested for leakage and contamination.
if the test reveals the presence of contamination in excess of 0.005 Ci of removable contamination, the source shall be immediately removed from service and decontaminated, repaired, or disposed o, en accordance with Commission regulations. A report shall be prepared and submitted to the Regional Administrator, U.S.
Nuclear Regulatory Commission, Region IV, within 30 days of the date the leak test result greater than 0.005 Ci is discovered. The
)
V-4 Amendment No 32
report shall specify the source involved, the test results, and corrective action taken. Records of leak test results shall be kept l
in units of microcuries.
i b.
Each sealed source shall be tested for leakage and contamination by the licensee or other persons specifically authorized by the U.S.
Nuclear Regulatory Commission or an Agreement State. The test method shall have a detection sensitivity of at least 0.005 Ci.
{
c.
Each sealed source described in a. above (excluding startup sources and fission detectors previously subject to core flux) shall be tested for leakage and contamination as follows:
(1)
Sources in Use - At least once per 6 months for all sources containing radioactive material, other than hydrogen 3, with a half-life greater than 30 days and in any form other than gas.
(2)
Stored Sources Not in Use - Each sealed source and fission detector shall be tested prior to use or transfer to another
!icensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a i
i certificate indicating the last test date shall be tested prior to being placed into use.
i l
l l
V-5 Amendment No. 31
l TABLE V-1 l
i Deleted l
l 1
V-6 Amendment No. 32
A l
l.
)
l Deleted I'
Fig. V-1 Dosimeter Locations for Stations near HBPP V-7 Arnendment No. 32
6 e
N C')
d Z.
8-
.N h.
8a 8
E
- E I
8 e
Q m
to 6
so N..
.s u.
]
1 I'l i
l 1
i i
l l
i i
i
[.
i-l I
Deleted I
i 1
Fig. V-3 HBPP Groundwater Monitoring Wells V-9 Amendment No. 32
VI.
WASTE DISPOSAL SYSTEMS A.
Deleted 1.
Deleted 2.
Deleted B.
OPERATING LIMITS AND REQUIREMENTS 1.
Liauid Radioactive Waste System a.
Deleted l
l b.
Deleted c.
Deleted d.
Deleted e.
Deleted f.
The radiological inventory of wastes in outdoor tanks that are not i
capable of retaining or treating tank overflows shall not exceed 0.25 Ci.
2.
Solid Radioactive Waste System a.
The radiological inventory of wastes within the solid radioactive waste system shall not exceed 1000 Ci.
VI - 1 Amendment No. 32
b.
Deleted c.
Deleted i
3.
Deleted 1
4
)
l I
i l
l l
1 I
l 1
1
)
VI - 2 Amendment No. 32
Vll.
ADMINISTRATIVE CONTROLS l
A.
RESPONSIBILITY The Plant Manager shall have the overall onsite responsibility for activities associated with Unit 3. He shall be accountable for adherence to the operating limits and requirements contained in these Technical Specifications. He shall delegate these responsibilities to other specified members of the Plant staff during his absence.
B.
ORGANIZATION l
l l
Onsite and offsite organizations shall be established for plant operation and corporate management, respectively." The onsite and offsite organizations shall l
include the positions for activities affect:ng the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be established l
and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of I
organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Senior Vice President and General Manager, Nuclear Power Generation Department Procedures, l
Vil-1 Amendment No. 24 L
b.
The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
c.
The Senior Vice President and General Manager, Nuclear Power Generation shall have corporate responsibilities for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence frorn operating pressures.
i C.
PLANT STAFF 1.
Reauirements for the Shift Operatina Oraanization The operating shift organization shall consist of a minimum of two a.
persons, one of which shall be a Certified Fuel Handler. In addition to the Certified Fuel Handler, the other shift position shall be at least an Auxiliary Operator.
b.
At least one Certified Fuel Handler shall be onsite when fuel is in the spent fuel storage pool.
l l
Vil - 2 Amendment No. 31
c.
The Unit 3 control room shall be continuously manned or, as an alternative, audible and visual annunciation of all alarms in Unit 3 shall be provided at a continuously manned control station in Units 1 or 2. A common annunciator may be used for all such alarms.
l i
d.
SPENT FUEL shall only be handled under the following conditions:
i o
SPENT FUEL handling operations shall be under the direct supervision of a member of the plant management staff who is a Certified Fuel Handler.
o At least one Certified Fuel Handler shall be present at the l
l location of each fuel movement.
2.
Plant Staff Qualifications The minimum qualifications 'for members of the plant staff shall be the 1
following:
a.
Plant Manager (1)
Ten years of responsible power plant experience, of which 1 year shall be nuclear power plant experience.at A maximum of l
l' An individual may be assigned to any of these positions without meeting the
)
requirements if a sufficient number of other persons who meet those requirements are assigned to the plant full time to assist the individual until the minimum qualifications are met.
a' Nuclear experience includes experience at HBPP during operations or during SAFSTOR.
Vil - 3 i
L s
a
(
4 years of the remaining 9 years of experience may be fulfilled on a one-for-one time basis by academic training in an engineering or scientific field generally associated with power production.
(2)
Certified Fuel Handler in accordance with the Humboldt Bay Power Plant (HBPP) Fuel Handler Certification Training Program.
b.
Supervisor of Operations 1
l (1)
Eight years of responsible power plant experience, of which 1 year shall be nuclear power plant experience. A maximum of 4
~
l years of experience may be fulfilled on a one-for-one time basis by academic training in an engineering or scientific field generally associated with power production.
(2)
Certified Fuel Handler in accordance with the HBPP Fuel Handler Certification Training Program.
l c.
Senior Power Production Engineer (Technical Manager) l (1)
Bachelor's degree or the equivalent in an engineering or l
i scientific field.
(2)
Four years in responsible positions related to power generation, of which 1 year shall be nuclear industry experience.
Vil - 4 Amendment No. 31 l
i (3)
Thorough knowledge of radiation and criticality safety requirements and practices, including safety requirements specifically related to maintenance and operations under radioactive contamination conditions.
l (4)
Certified Fuel Handler in accordance with the HBPP Fuel Handler Certification Training Program.
i d.
Senior Radiation Protection Engineer (Radiation Protection Manager)
(1)
Bachelor's degree or the equivalent in engineering or a scientific field inauding some formal training in radiation protection.
1 (2)
At least 5 ysars of professional experience in applied radiation protection. (A master's degree may be considered equivalent to 1 year of professional experience, and a doctorate may be considered equivalent to 2 years of professional experience where course wor 3 related to radiation protection is involved.)
At least 3 years of this experience should be in applied radiation protection in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power stations.
(3)
Specialized knowledge of health physics, thorough knowledge of radiation and criticality requirements and practices, and knowledge of related regulatory requirements and practices.
l f
I Vil - 5 Amendment No. 31
i o
e.
Supervisor of Maintenance (1)
Seven years of responsible power plant experience or applicable industrial experience, of which a minimum of 1 year shall be nuclear power plant experience. A maximum of 2 years of the remaining 6 years of power plant or industrial experience may be fulfilled by satisfactory completion of academic or related technical training on a one-for-one time basis.
(2)
Thorough knowledge of safety requirements specifically related to maintenance under radioactive contamination conditions, f.
Quality Control Supervisor I
(1)
Five years of responsible power plant experience or applicable industrial experience, of which a minimum of 1 year shall be experience in the nuclear field. A maximum of 2 years of the remaining 4 years of power plant or applicable industrial experience may be fulfilled by satisfactory completion of academic or related technical training on a one-for-one time basis.
(2)
Thorough knowledge of nuclear materials handling, I
safeguards, and quality assurance methods and procedures.
i g.-
Assistant Plant Manager / Power Plant Engineer Vil - 6 Amendment No. 31
I (1)
Bachelor's degree or the equivalent in an engineering or scientific field.
l-I (2)
Four years in responsible positions related to power Generation, of which 1 year shall be nuclear industry experience.
(3)
Thorough knowledge of radiation and criticality safety requirements and practices, including safety requirements i
l specifically related to maintenance and operations under i
radioactive contamination conditions.
(4)
Certified Fuel Handler in accordance with the HBPP Fuel j
Handler Certification Training Program.
h.
Certified Fuel Handler (1)
Hig.h school diploma or equivalent.
(2)
At least 1 year of experience at HBPP.
(3)
Satisfactory completion of HBPP Fuel Handler Certification Training Program.
l 3.
Fire Protection Prooram a.
The Plant Manager is responsible for the fire protection program. A member of the Engineering Staff serves as Fire Marshal with responsibilities for periodic evaluation Vll-7 Amendment No. 31
o l
ma ntain ng cu nt and e v fi protecti n prog am.
b.
At least three members of the shift operating organization shall be trained members of the fire brigade. These individuals shall be available to respond in the event of a fire emergency in the unit. The fire brigade shall not include any personnel required for other essential functions during a fire emergency.
i 4.
Trainina a.
A training program shall be administered to certify members of the Plant staff as certified fuel handlers. The training program shall include the following:
(1)
Reactor theory (as it applies to storage of spent reactor fuel)
(2)
Spent fuel handling and storage equipment - design and operating characteristics (3)
Monitoring and control systems (4)
Radiation protection (5)
Normal and emergency procedures l
l Vil - 8 Amendment No. 31
(6) Administrative controls applicable during SAFSTOR period L
Successful completion of the training program shall be certified by the l
Plant Manager or his delegate.
1 l
l b.
The Fuel Handler Certification Training Program shall include a continuing requalification program which shall include training in each i
of the above areas on at least a 2-year cycle.
c.
A training program for the fire brigade shall be maintained under the direction of the Fire Marshal and shall meet or exceed the requirements of NFPA 27, " Standard for Private Fire Brigades," 1976, d.
An initial training program shall be administered for radiation and
~
process monitors (RPMs) which will include the following:
(1)
Nuclear technology (2)
Plant design and operation (as related to SAFSTOR conditions)
(3)
Chemistry (4)
Radiochemistry (5)
Emergency plan and procedures (6)
Radiation protection (7)
Review of 10 CFR 19,20,61, and 71.
A retraining program covering the above topics shall be administered l
on a 2-year cycle.
l Vil - 9 Amendment No. 31
(
e D.
REVIEW AND AUDIT i
l 1.
Plant Staff Review Committee l
a.
Purpose The Plant Staff Review Committee (PSRC) shall meet on a regular basis to review overall operating and maintenance experience, proposed changes and tests, adequacy of procedures, and other matters that may have a bearing on nuclear or radiological safety at the plant.
b.
Membership 1
~
l The PSRC shall be composed of members of the Plant staff who have responsibility in the areas of; i
Operations e
Electrical maintenance e
Mechanical maintenance Instrumentation and control maintenance Radiation protectio-e Nuclear engineering e
Quality control.
e l
Minimum membership shall include:
Plant Manager (Chairman)
Supervisor of Operations e
Vil - 10
l
[
Supervisor of Maintenance l
l Senior Power Production Engineer Senior Radiation Protection Engineer l
-Quality Control Supervisor Assistant Plant Manager / Power Plant Engineer c.
Attemates l
(1)
In the absence of a regular member, the Chairman may designate an alternate from the plant staff to carry out review j
functions.
l l
(2)
The Chairman shall decignate a regular member to serve as chairman in his absence.
d.
Meeting Frequency i
Once per calendar quarter and at other times at the discretion of the Chairman.
l e.
Quorum l
A quorum shall consist of four regular members or three regular i
members and an alternate.
f.
Responsibilities (1)
The PSRC shall review the following items prior to implementation to determine if a change in the Technical Vil - 11 Amendment No. 31
l I
l:
Specifications or an unreviewed safety question as defined in 10 CFR 50.59 is involved, and shall render such l
determinations in writing:
l l
a)
Proposed tests and experiments determined by a l
Committee ms.nber to have nuclear safety significance.
b)
Proposed changes or modifications to Unit 3 systems or equipment.
c)
Proposed normal, abnormal, and emergency operating procedures, maintenance procedures, security j
procedures, administrative procedures, and other procedures determined by a Committee member to be i
significant to the maintenance of Unit 3 in SAFSTOR.
{
)
d)
Proposed changes to approved procedures of the type described in item c) above.
e)
Proposed changes to the Technical Specifications.
(2)
The PSRC shall periodically review:
a)
Approved procedures of the type described in item (1) c) above for currentness and applicability.
b)
Maintenance and surveillance testing experience to ensure safe and efficient maintenance of the Unit and to i
Vil-12 i
determine if changes to equipment or procedures are needed.
(3)
The PSRC shall investigate any violation of these Technical 4
Specifications and prepare and forward a report to the Senior Vice President and General Manager, Nuclear Power Generation and the Nuclear Safety Oversight Committee (NSOC) cevering their evaluation and recommendations to prevent recurrence.
l l
(4)
The PSRC shall conduct a biennial review of:
l
)
l a)
The Plant Security Plan and implementing procedures to determinelhe need for changes in the plan or its implementing procedures.
b)
The Site Emergency Plan and its implementing procedures to determine the need for changes in the plan or its implementing procedures.
4 g.
Authority (1)
The PSRC shall recommend to the Plant Manager approval or disapproval of proposals reviewed under items f.(1) through (3) above.
W (2) The PSRC shall render written determnations regarding whether or not a proposed change or test or other such mattar which has been reviewed invoives an "unreviewed safety Vil - 13 Amendment No. 31
a K
question" as defined in 10 CFR 50.59(c) or a change in the Technical Specifications.
(3) in the event of disagreement between PSRC members on a matter affecting nuclear or radiological safety, a conservative course shall be followed as determined by the Plant Manager.
Records of such disagreements shall be included in the meeting minutes, described in item h. below, and distributed promptly.
h.
Records Minutes of each PSRC meeting shall be prepared and maintained at l
the Plant. Copies of mi6utes shall be sent to the Senior Vice l
President and General Manager, Nuclear Power Generation and to l
the NSOC.
1 2.
Nuclear Safety Oversicht Committee a.
Purpose The Nuclear Safety Oversight Committee (NSOC) shall function to provide independent review and audit of designated activities in the areas of; Nuclear power plant operations Nuclear engineering Vil - 14 Amendment No. 25
l Chemistry and radiochemistry Metallurgy e
Instrumentation and controls Radiological safety e
Mechanical and electrical engineering e
Quality assurance practices e
The NSOC shall report to and advise the Senior Vice President and General Manager, Nuclear Power Generation on those areas of l
responsibility specified in items 2.g. and 2.h. below.
l b.
Composition i
The NSOC shall be composed of a chairman and a minimum of four members. The NSOC Chairman and members shall be appointed in writing j
by the Senior Vice President and General Manager, Nuclear Power Generation. The NSOC Chairman shall have a minimum of six years of professional level managerial experience in the power field and the NSOC members shall have a minir.num of five years of professional level experience in the field of their specialty. The NSOC Chairman and all members shall have qualifications that meet or exceed the requirements and I
recommendations of Section 4.7 of ANSI /ANS 3.1-1978.
Vil - 15 Amendment No. 25 l
a 4
- c.
Deleted i
i d.
Consultants Consultants shall be utilized as determined by the NSOC Chairman to
- provide expert advice to the NSOC.
e.
Meeting Frequency The NSOC shall meet at least once per 6 months.
i f.
Quorum I
i A quorum of the NSOC necesse.ry for the performance of the NSOC function of these Technical Specifications shall be a majority (one-half I
or more) of the members, but no less than four.
l g.
Review The NSOC shall review:
l-(1) The safety evaluations for (1) changes to procedures, I
equipment, or systems, and (2) tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not c6nstitute an unreviewed safety question.
Vil - 16 Amendment No. 25 4
1 a
1 (2)
Proposed changes to procedures, equipment, or systems inat involve an unreviewed safety quettion as defined in 10 CFR 50.59.
(3)
Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59.
(4)
Proposed changes to Technical Specifications or the License.
(5)
Violations of codes, regulations, orders, Technical Specifications, license requirements, or laternal procedures or instructions having nuclear safety significance.
(6)
Significant operating abnormalities or deviations from normal and expected performance of Unit equipment.
l (7)
Events requiring written notification to the Commission.
l (8)
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or i
components that could affect nuc!aar safety.
(9)
The PSRC's reports and meeting minutes.
i i
h.
Audits Vil - 17 Amendment No. 25
D J
Audits of Unit activities shall be performed under the cognizance of the NSOC. These audits shall encompass:
j (1)
The conformance of Unit operation to provisions contained within the Technical Specifications and applicable license i
conditions - at least once per 12 months.
(2)
The performance, training, and qualifications of the entire Unit staff - at least once per 12 months.
(3)
The results of actions taken to correct significant deficiencies occun'ing in Unit equipment, structures, systems or methods of operation - at least once per 6 months.
l (4)
The performance of activities required by the Quality Assurance Program - at least once per 24 months.
l (5)
The Emergency Plan and implementing procedures - at least once per 24 months.
l (6)
The Security Plan and implementing procedures - at least once per 24 months.
(7)
The Fire Protection Program and implementing procedures -
at least once per 24 months.
1 Vil - 18 Amendment No. 25
~
O 4
l (8)
An independent inspection and audit of the Fire Protection and l-Loss Prevention Program by qualified offsite licensee l
personnel or an outside fire protection firm - at least once per i
12 months.
j i
(9)
An inspection and audit of the Fire Protection and Loss Prevention Program by a qualified outside fire consultant - at least once per 36 months.
i i.
Records Records of the NSOC activities, including minutes of meetings, i
reports of reviews, and audit reports shall be prepared, approved and l
distributed es required b'y the approved NSOC Charter.
E.
PROCEDURES 1.
Detailed Procedures Detailed written procedures, including applicable checkoff lists and instructions, shall be established, implemented, and maintained for significant activities associated with the maintenance of Unit 3 in SAFSTOR, including:
a.
Fuel handling operations (including removal and reinstallation of the spent fuel storage pool cover)
Vil-19 Amendment No. 25 u
O 4
b.
Normal startup, operation, and shutdown of systems and components required during SAFSTOR c.
Actions to be taken to correct specific and foreseen potential malfunctions of systems or components d.
Actions to be taken during emergency conditions involving unplanned releases of radioactivity 4
i e.
Abnormal and emergency operation of all systems and components required to maintain the SAFSTOR condition of the Plant f.
Plant Security Plan implementation g.
Surveillance activities required to demonstrate compliance with the Technical Specifications i
h.
Calibration of instrumentation used to demonstrate compliance with Technical Specifications i.
Shipping and disposal of radioactive materials j.
Procedure Review All procedures described in item 1 above, and changes thereto, sha!! be reviewed by the PSRC and approved by the Plant Manager prior to Vil-20 Amendment No. 32 m
O 4
implementation, except as provided in items 3 and 4 below.
3.
Procedure Chanaes Rules shall be established that provide methods by which temporary changes can be made to approved procedures, including the designation of these persons authorized to approve such changes. Temporary changes that clearly do not change the intent of the approved procedure from the standpoint of nuclear safety may be approved by two members of the plant management staff, at least one of whom is a Certified Fuel Handler. Such changes shall be documented and, if appropriate, incorporated into the next revision of the affected procedure.
4.
Emeraencies Not Covered by 5 Procedure in the event of an emergency not covered by an approved procedure, operations personnel shall be instructed to take action to minimize personnel injury and damage to the facility.
l F.
RADIOACT8VE EFFLUENT CONTROLS PROGRAM l
A program shall be provided conforming with 10 CFR 50.36a for the co;1 trol of radioactive effluents and for maintaining the doses to members of the public l
from radioactive effluents as low as reasonably achievable (ALARA). The program (1) shall be contained in the ODCM, (2) shall be implemented by operating i
Vil - 21 Amendment No. 32
procedures, and (3) shall include remedial actions to be taken whenever the I
program limits are exceeded. The program shall include the following elements:
1.
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2.
Limitations on the instantaneous (average over a one-hour period) concentrations of radioactive material released in liquid emuents to Humboldt Bay conforming to ten times the effluent concentration lirr.its of 10 CFR Part 20, Appendix B, Table 2, Column 2, 3.
Monitoring, sempling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM, 4.
Limitations on the annual and quarterly doses or dose commitment to l
l a member of the public from radioactive materials in liquid j
effluents released to Humboldt Bay conforming to the dose design objectives of Appendix I to 10 CFR Part 50, 5.
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in j
the ODCM at least every 31 days, 6.
Limitations on the operability and use of the liquid efficent treatment systems to ensure that the appropriate portions of these systems are
)
i Vil - 22 Amendment No. 32 L
ussd to reduce relsasss of radioactivity whsn the projsetsd doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to the dose design objectives of Appendix i to 10 CFR Part 50, 7.
Limitations on the dose rate resulting from radioactive material released in j
gaseous effluents to areas beyond the site boundary shall be established as follows:
a.
For noble gases: Less than or equal to an instantaneous dose rate (average over a one-hour period) of less than or equal to 500 mremlyr to the total body and less than or equal to 3000 mrem /yr to the skin, and b.
For tritium and radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate (averaged over a one-week period) of 1500 mremlyr to any organ.
8.
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50, 9.
Limitations on the annual and quarterly doses to a member of the public from tritium and ai! radionuclides in particulate from with half-lives greater than 8 days in gaseous effluents released to areas beyond the site boundary conforming to the dose design objectives of Appendix l to 10 CFR part 50, and 10.
. Limitations on the annual dose or dose commitment to any member of Vil - 23 Amendment No. 32 t
Q O
the public due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR part 190.
G.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
' A program shall be provided to monitor the radiation and radionuclides in the environs of the facility to provide assurance that the baseline conditions established by the Environmental Report submitted as Attachment 6 to the j
SAFSTOR license amendment request are not deteriorating. The program shall provide (1) onsite environmental monitoring consisting of a continuous sampler in the discharge canal, fenceline dosimetry stations, and groundwater monitoring wells, and (2) oifsite environmental monitoring consisting of dosimetry stations that represent a gradient downwind in the prevailing wind direction. The program shall (1) be contained in the ODCM and (2) include the following:
1.
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,-
i 2.
Participation in an Interlaboratory Comparison Program to ensure that i
independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
H.
SITE EMERGENCY PLAN The Site Emergency Plan shall provide the necessary prearrangement and organi7r?ian of personnel to deal effectively with emergencies at the Plant so as to Vil-24 Amendment No. 32
minimize radiation exposure to Plant personnel and the general public. The plan shall describe the specific duties of Plant personnelin the event of an accident or any unplanned incident producing high radiation levels. Drills and exercises described in the Emergency Plan sha!I be performed to ensure that all Plant personnel are thoroughly familiar with the plan.
I.
SURVEILLANCE TESTING Testing of system components, monitors, and other equipment to which these Technical Specifications apply shall be as described in Sections til through VI.
Each surveillance test shall be performed within the specified time interval with:
A maximum allowable extension not to exceed 25% of the test interva!
A total interval time for any three consecutive test intervals not to exceed 3.25 times the specified test interval Appropriate tests shall also be performed following maintenance on these systems f
that could impair their operation.
f J.
REPORTING REQUIREMENTS in addition to the applicable reporting requirements of 10 CFR, the following reports shall be submitted:
l 1.
Annual Report An Annual Radiological Monitoring Report shall be submitted to NRC within Vil - 25 Amendment No. 32
90 days of January 1 of each year. The report shall include (1) a description of the results of the facility radiation surveys and the status of the facility, i
and (2) the Annual SAFSTOR Radiological Environmental Monitoring Report. The Annual SAFSTOR Radiological Environmental Monitoring Report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the ODCM.
1 2.
Nonroutine Reports a.
The NRC Operations Center shall be notified of emergency and j
i nonemergency events in accordance with 10 CFR 50.72.
q b.
Reportable events shall be reported in accordan.:e with 10 CFR 50.73.
f 3.
Annual Effluent Release Report l
l The Annual Effluent Release Report covering the previous calendar year shall be submitted to the NRC before April 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a.
i Vil - 26 Amendment No. 32
l 4.
Special Reports If the calculated dose to any member of the general public exceeds the 40 CFR 190 limits, a Special Report shall be made to the Regional Administrator, NRC Region IV, within 30 days. This report shall include an analysis of the estimated dose received by a member of the public from uranium fuel cycle sources for the applicable consecutive 12-month period.
The repcrt shall also describe the corrective actions planned to reduce subsequent exposures and io prevent recurrence of the event. The Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and include the information specified in 40 CFR 190.11(b). Submittal of the report is considered a timely request, and variance is granted until NRC Staff action on the request is completed.
K RECORD RETENTION 1.
Five-Year Retention All records and logs relative to the following arsas shall be retained for at i
least 5 years:
1 a.
Records and logs of normal SAFSTOR operations.
b.
Records and logs of principal maintenance activities, including inspection, repair, substitution, or replacement of principal items of equipment described in the Technical Specifications.
I c.
Reportable Occurrence Reports i
1 Vil-27 Amendment No. 32
d.
Records of periodic checks, inspections, and calibrations performed to verify that surveillance requirements are being met.
e.
Records of radioactive shipments.
f.
Records of sealed source leak tests and results.
g.
Records of the annual physical inventory of all source material of record.
h.
Records of tests or experiments associated with SPENT FUEL storage.
1 i.
Records of changes made in operating procedures.
2.
SAFSTOR Duration All records relative to the following areas shall be retained for the duration of I
SAFSTOR:
a.
Records and prints of changes made to the Plant.
b.
Records of spent fuel inventory, transfers of fuel, and assembly histories.
c.
Records of plant radiation and contamination surveys.
Vil-28
d.
Records of offsite environmental monitoring surveys.
e.
Records of radiation exposure for all plant personnel, including all contractors and visitors to the plant, in accordance with 10 CFR 20.
f.
Records of radioactivity in liquid and gaseous wastes released to the environment.
g.
Records of training and qualification for current members of the plant staff.
h.
Minutes of meetings of the PSRC and NSOC.
i.
Records of Quality Assurance activities required by the SAFSTOR Quality Assurance Plan.
j.
Records of reviews performed for changes made to procedures or equipment, or reviews of tests and experiments pursuant to the Final Hazard Summary Report (FHSR).
k.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
L.
RADIATION PROTECTION PROGRAM Radiation control procedures shall be prepared, approved, adhered to, and made i
I Vil - 29 Amendment No. 32
t.
available to all plant personnel. Ti:sse procedures shall show permissible radiation 1
exposure and shall be concistent with the requirements of 10 CFR 20. The l
radiation protection program shall be organized to meet the requirements of 10 CFR 20.
M.
Less Than or Ecual to 1000 mr/hr I
i Pursuant to paragraph 20.1601(c) of 10 CFR Part 20, in lieu of the " control device" or " alarm signal" required by paragraph 20.1601(a), each high l
radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mr/hr at 30 cm (12 in.) from the radiation source or from any surface that the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area, and entrance thereto shall be controlled by requiring issuance of special work permits (SWPs). Individuals qualified in radiation protection procedures (e.g.,
Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the SWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mr/hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitting device that continuously indicates the radiation dose rate in the area.
Vll - 30 Arrendment No. 32
b.
A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be madi after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.
c.
An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified.
2.
Greater Than 1000 mr/hr In addition to the requirements of Specification Vll.M.1, areas acces:;ible to personnel with radiation levels greater than 1000 mr/hr at 30 cm (12 in.) from the radiation source or from any surface that the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty or Health Physics supervision. Doors shall remain locked except during periods of access by personnel under an approved SWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the SWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualiEed in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
Vil - 31 Amendment No. 32
N.
PROCESS CONTROL PROGRAM CHANGES Changes to the PCP:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification Vll.K2.k. The documentation shall contain:
a.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b.
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, i
State, or other applicable regulations.
l 2.
Shall become effective after review and acceptance by the PSRC and the approval of the Plant Manager.
O.
OFFSITE DOSE CALCULATION MANUAL CHANGES l
Changes to the ODCM:
l l
1.
Shall be required and records of reviews performed shall be retained as i
required by Specification Vll.K2.k. This documentation shall contain:
l-a.
Sufficient informatio6 to support the change together with the appropriate analyses or evaluations justifying the change (s) and.
Vil - 32 Amercment No. 32
l o
l b.
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 1
CFR 50.36a, and the guidelines of Appendix ! to 10 CFR Part 50 for the annual dose or dose commitment and not adversely impact the accuracy or reliabi!ity of effluent, dose, or setpoint calculations.
2.
Shall become effective after review and acceptance by the PSRC and the approval of the Plant Manager.
3.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,
month / year) the change was implemented.
l l
l Vil - 33 Amendment No. 32