ML20247L331
| ML20247L331 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/25/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245F906 | List: |
| References | |
| NUDOCS 8906020137 | |
| Download: ML20247L331 (11) | |
Text
.
@O AIGQ
,f[.
,'o UNITED STATES g
.-y 7,
NUCLEAR REGULATORY COMMISSION l.
'G
' l-W ASHINGTON. D. C. 20555
\\...../
ARKANSAS F0HER AND LIGHT COMPANY DOCKET N0. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDHENT TO FACILITY OPERATIllG LICENSE Amendment No.121 License No. DPR-51 1.
The fluclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (thelicensee)datedDecember 12, 1986, complies with the standards ar.d requirements of the Atcmic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of tl.e Act, and the rules and regulations of the Comission; 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 compliar.ce with the Connission's regulations; D.
The issuance of this licerse amendment will nct be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
l l
8906020137 890525 j
PDR ADOCK 05000313
~
p PDC
L.
d
. '2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license
. amendment, and Paragraph 2.C.(2) of Facility Operating License No.
DPR-51 is hereby amended to read as follows:
(2) Technical Specifications The Technica1' Specifications contained in Appendices A and B, as revised through Amendment No.121, are hereby incorporated in the license. The licensee shall operate the _ facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
A B
Freder J. Hebdon, frector Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects
.0ffice of Nuclear Reactor Regulation
Attachment:
Changes-to the Technical Specifications Date of Issuance: May 25, 1989 4
i
___________________________-__2
_- g-ATTACHMENT TO LICENSE AMENDfiENT NO. 121 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Revise the following pages of the Appendix "A" Technical Specifications lwith the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of chance.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 36 36 37 37 74 74 75a 79 79 80 80.
82 82 105 105 106.
106 110t 110t 110z 1102 i
1 l
l 1
3.' 3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING AND REACTOR BUILDING SPRAY SYSTEMS 4
Applicability Applies'to the' emergency core cooling, reactor building cooling and reactor building spray systems.
Objectivity To; define the conditions necessary to assure immediate availability of the emergency core cooling, reactor building cooling and reactor building spray
. systems.
Specification
-3.3.1 The following equipment shall be operable whenever containment integrity is established as required by Specification 3.6.1:
(A). One reactor building spray pump and its assoc'iated spray
' nozzle header.
(B) One reactor building cooling fan and its associated cooling unit.
(C).Two out of three service water pumps shall be operable, powered from independent essential buses, to provide redundant and independent flow paths.
(D) Two engineered safety feature actuated low pressure injection pumps shall be operable.
(E) Both low pressure injection-coolers and their cooling water supplies shall be operable.
(F) Two BWST level instrument channels shall be operable.
(G) Theboratedwaterstoragetankshallcontainalevelof37.5[1.5 ft.
(362,000
- 13,000 gallons) of water having a concentration of 2470 i 200 ppm boron at a temperature not less than 40F.
The manual valve on the discharge line from the borated water storage tank shall be locked open.
(H) The four reactor building emergency sunp isolation valves to the LPI system shall be either manually or remote-manually operable.
I I
l l
i l
1 Amendment No. 28, 29, 121 36
r J.$
.(I) 'The engineered safety features' valves associated with each of the above systems shall be operable or locked 'in the ES position.
3.3.2 In addition to 3.3.1 above, the following ECCS equipment shall be operable when the reactor coolant system is above 350F and:
irradiated fuel is.in the core:
a (A) Two out of three-high pressure injection (makeup) pumps'shall be maintained. operable, powered lfrom independent essential buses, to provide redundant and independent flow paths.
(B). Engineered safety featu'res valves assoc'iated with 3.3.2.a above shall be operable or locked in the ES position.
3.3.3 In' addition to 3.3.1'and 3.3.2 above, the following ECCS equipment shall be operable when the reac',or coolant system is above 800 psig:
(A) The.two core flooding tanks shall each contain an indicated minimum of 13 1 0.4 feet (1040 30 ft8) of borated water at 600
- 25 psig.
(B) Core flooding tank boron concentration'shall not be less than
-2270 ppm boron.
(C) The electrically operated discharge valves from the core flood tanks shall be open and breakers locked open and
- tagged.
(D) : One of the two pressure instrument channels and one of the
.two level instrument channels per core flood tank shall be operable.
3.3.4 The reactor shall not be made critical unless the following equipment in addition to 3.3.1, 3.3.2,.and 3.3.3 above is operable.
(A) Two reactor building spray pumps and their associated spray nozzle headers and two reactor building emergency cooling fans and associated cooling units powered from operable independent emergency buses.
(B) The sodium hydroxide tank shall contain an indicated 34}f.0 ft.of18[2.8 wt % solution sodium hydroxide (19,500 lb. 1 2500 lb.).
=
(C) All manual valves in the main discharge lines of the sodium 3
hydroxide tanks shall be locked open.
l Amendment No. 26, 25, 121 37
_._______-__L
~
~'
Table 4.1-3 MINIMUM SAMPLING AND ANALYS15 FREQUENCY Item Test
.Frecuency
- a. Gamma' Isotopic Analysis
- a. Bi-weekly (7)
- Samples
- b. Gross Activity Determination
- b. 3 times / week and at least every third day (1)(6)(7)
- c. Gross Radiofodine
- c. Weekly (3)(6)(7)-
Determination
- d. Dissolved Gases
- d. Weekly (7) 4
- e. Chemistry (C1, F, and 0 )
- e. 3 times / week (8) 2
- f. Boron Concentration
- f. 3 times / week
- g. Radiochemical Analysis for
- g. Monthly (7)
E Determination (2) (4)
- 2. Borated Water Boron Concentration Weekly and after Storage Tank Water each makeup Sample
- 3. Core Flooding Tank Boron Concentration Monthly and after Sample each makeup
- 4. Spent Fuel Pool Boron Concentration Monthly and after Water Sample each makeup (9)
- 5. Secondary Coolant
- a. Gross Radiofodine
- a. Weekly (5)(7)(10)
Samples Concentration
- b. Isotopic Radiciodine
- b. Monthly (7)(10)
Concentration (4)
Notesi (1)
A gross radioactivity analysis shall consist of the quantitative measurement of the total radioactivity of the primary coolant in units of pCi/gm. The total primary coolant activity shall be the sum of the degassed beta gamma activity and the total of all identified gaseous activities 15 minutes after the primary system is sampled. Whenever the gross radioactivity concentration exceeds 10% of the limit specified in the Specification 3.1.4.1 or increases by 10 pCi/gm from the previous mcasured level, the frequency of sampling and analyzing shall be increased to a minimum of once/ day until a steady activity level is established.
L d
Amendment No. 12, 39, 121.
L_
ni
l 1
\\
- 4. 4 REACTOR BUILDING 1
l 4.4.1
. Reactor Buildino Leakace Tests.
{
Applicability Applies to the reactor building.
Objective To verify that leakage from the reactor building is maintained within allowable limits.
i Specification, 4.4.1.1 Integrated Leakage Rate Tests i
4.4.1.1.1 Design Pressure Leakage Rate i
The maximum allowable integrated leakage rate, L, from the reactor I
building at the 59 psig design pressure, P, shall not exceed 0.20 weight percent of the building atmosphere Et that pressure per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
'4.4.1.1.2 Testing at Reduced Pressure 1
The periodic integrated leak rate test may be performed at a test pressure, P, of 30 psig provided the resultant leakage rate, L '
doesnotexheedapre-establishedfractionofL,determinedast l
follows:
Prior to reactor operation the initial value of the integrated a.
leakage rate of the reactor building shall be measured at design pressure and at the reduced pressure to be used in the periodic integrated leakage rate tests.
The leakage rates thus measured i
shall be identified as L, and L respectively, g
b.
L. shall not exceed L, L for values of L g
g b41ow 0.7 g
am am c.
L shall not exceed L, F for values of L above0.7 t
g 7
a am
(
d.
If.L /L is less than 0,3, the initial integrated test results sha1Nbe,IubjecttoreviewbytheNRCtoestablishanacceptable l
valua of L
- t 1
79 Amendment No. 121
q 2,
~
l 4.4.1.1.5 Conditions for Return to Criticality j
If L*I 5% L )
is less than L (L,
7 to g
q or If L is less than L (L, "I 75% L,)
4.4.1.1.6 Corrective Action Retest
.a If L is greater than L local leak tests will then be i
4 perfEmed and the requirI8, repairs made. The integrated leakage test need not be repeated provided local measured leakage reduction achieved by repairs of individual leake reduces the reactor building's overall mensured leakage 1
rate sufficiently such that L, is less than L g
to' 4.4.1.1.7 Report of Test Results The initial test report shall include a schematic arrangement of the leakage rate measurement system, the instrumentation used, the supplemental test method and the
{
i test program selected as applicable to the initial test and all subsequent periodic tests. The report shall contain an analysis and interpretation of the leakage rate test data to the exte:1. necessary to demonstrate the acceptability of the reactor buildings leakage rate in meeting the acceptance criteria.
4.4.1.2 Local Leakage Rate Tests 4.4.1.2.1 Scope of Testing The local leak rate shall be measured for components in j
the following categories:
Reactor building penetrations whose design a.
incorporates resilient seals, gaskets, or sealant compounds; piping penetrations fitte with expansion bellows, l
b.
Air lock door seals, including operating mechanism i
and penetrations with resilient sealt which are 1
part of the reactor building pressure boundary in the air lock structures.
S Equipment and access doors with resilient seals or c.
l gaskets (seal-welded doors are excluded).
d.
Components other than those listed in items a,b, and c above which develop leaks inservice and i
l 81
.R
e
.l-1 E
4.8. EMERGENCY FEEDWATER-PUMP TESTING l
Applicability.
Applies to the periodic testing of the turbine and electric' motor driven f
emergency feedwater pumps.
j Objective
)
To verify that the emergency feedwater pump and associated valves are operable.
Specificati_on 4.8.1 Each EFW train shall be demonstrated operable:
a)
By verifying on a STAGGERED TEST BASIS:
1.
at least once per 31 days or upon. achieving hot shutdown following a plant heatup and prior to criticality, that.
the turbine-driven pump starts, operates for a' minimum 1 1
1200 psig at a flow of 1 500 gpm through the test loop flow path.
2.-
at least once per 31 days by verifying that the motor driven EFW pump starts, operates'for a minimum of 5 minutes and develops a discharge pressure of g 1200 psig at a flow of 1500 gpm thorough the test loop flow path.
5)
At. least once per 31 days by verifying that each valve
'(manual, power operated or automatic) in each EFW flowpath that is not locked, sealed, or otherwise secured in position, is in its correct position.
c)
Prior to, exceeding 280*F reactor coolant temperature and after any EFW flowpath manual valve alterations by verifying that each manual valve in each EFW flowpath which, if mispositioned may degrade EFW operation, is locked in its correct position.
d)
At least once per 92 days by cycling each motor-operated valve in each flowpath through at least one complete cycle.
e)
At least once per 18 months by functionally testing each EFW train and:
1)
Verifying that each automatic valve in each flowpath actuates automatically to its correct position on receipt of an actuation signal.
Amendment No. 25, 55, SI, 121 105 i
+
L,,_,__,_a
_3
I 4.2'1 SPRENKLER SYSTEMS l
--Applicability Applies to surveillance of the sprinkler systems which are required to be operable by Specification 3.18.
Objective To assure that the various sprinkler systems are available and operable when needed.
Sote'ification 4.21.1 The cable spreading room sprinkler system shall be demonstrated operable at least once per 31 days by verifying that the system is aligned to the fire pumps.
4.21.2 The sprinkler systems located in the four reactor building cable l
penetration areas and four. cable penetration rooms shall be demonstrated operable:
At least once per 31 days by verifying that each system is l
a.
aligned to the fire pumps; b.
At least once per 12 months by cycling each testable valve in the flow paths through at least one complete cycle of full' travel.
4.21.3 The sprinkler systems located in the two emergency diesel I
generator rooms and two diesel generator fuel vaults shall be demonstrated operable:
At least once per 31 days by verifying that each system is a.
aligned to the fire pumps; 1
b.
At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel; c.
At least once per 18 months by inspection of the spray headers to verify their integrity.
Bases.
The cable spreading room sprinkler system is a wet pipe system actuated only by heat action on the fusible head sprinkler.
The only maintainable aspect of the system is the verification of system alignment.
The sprinkler systems in the four cable penetration areas and four cable penetration rooms are manually-operated closed-head (fusible head) systems t
I-which are remotely operated from the control room.
(
The sprinkler systems in the two emergency diesel generator rooms and two diesel generator fuel vaults are manually-operated open-head systems which are remotely operated from the control room.
The required inspections will assure availability of the various sprinkler systems when they are needed.
Amendment No. 35, 121 110t y
.e Lw-_--__-_--
b
l
. 'n 4.26 REACTOR BUILDING PURGE VALVES Applicability i
This specification applies to the reactor building purge supply and exhaust j
isolation valves.
Objective l
To assure reactor building integrity.
j Specification 4.26.1 The reactor building purge supply and exhaust isolation valves shall be determined ' closed at least once per 31 days when.
containment integrity is required by: TS 3.6.1.
l 4.26.2 Prior to exceeding conditions which require establishment of reactor building integrity per TS 3.6.1, the leak rate of the purge supply and exhaust isolation valves shall be verified to be 4
within acceptable. limits per TS 4.4.1, unless the test.has been
~
successfully completed within the last three months.
Bases Determination of reactor building purge valve closure will ensure that reactor building-integrity is not unintentionally breached.
l As a result of Generic Issue B-20, " Containment Leakage Due to Seal Deterioration," it was concluded that excess leakage past valve resilient 1
seals.is typically caused by severe environmental conditions and/or wear due to use.
Recommended leak test frequencies of three months are deemed to be
(
adequate to detect seal degradation of resilient seals.
The three month test need not be conducted with the precision of the Type C 10CFR50,. Appendix J criteria, however the test must be sufficient to detect degradation.
l I
l Amendment No. 55, 79, 121 110Z l
g
.