ML17278A887
| ML17278A887 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/27/1986 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17278A886 | List: |
| References | |
| GL-85-19, TAC-61641, NUDOCS 8606060047 | |
| Download: ML17278A887 (5) | |
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3/4.4. B SPECIFIC ACTIVITY ArTP CHNEHT lQ+
LIMITING CONDITION FOR OPERATION b.
Less than or equal to 100/E mfcrocurfes per gram.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, and 4.
ACTION:
a.
In OPERATIONAI CONDITION 1, 2, or 3 wfth the specific activfty of
the primary cool~a t; 1.
Greater than 6.&mfcrocurie per gram DOSE EQUIVALENT I-131 but osv.
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The provisions of Speci@)cation 3.0.4 are not applicable.
3.4.5 The specific activity of the primary coolant shall be limited to:
a.
Less than or equal to 0.2 microcurie per gram DOSE E/UIVALENT I-131, and 2.
Greater than 100/E mfcrocuries ~r gram, be fn at least HOT SHUTDOWN with the main wteamline isolation valves closed within
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12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
In OPERATIONAL CONDITION 1, 2, 3, or 4,'ith the sp'ecf.ic activity of the primary coolant greater than 0.2 microcurie per,gram DOSE EqUIVALENT I-131 or greater than 100/Z microcuries per gram, per form the sampling and analysis requirements of Item 4a of Table 4.4.5-1 until the specific activity of the primary coolant is restored to.
within fts limit.
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AYVOCH~a,wy REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION Continued ACTION:
c (Continued)
In OPERATIONAL CONDITION 1 or 2, Hth:
1.
THERMAL POWER changed by more than 15 of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />", or 2.
The off-gas level, at the 'SJAE, increased by more than 15,000 microcuries per second in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during steady-state operation at release rates less than 100,000 microcuries per second, or II 3.
The off-gas level, at the SJAE, increas~d by more than 15 in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during steady-state operation at release rates greater than 180,000 microcuries per second, perform the sampling and analysis requirements of Item 4b of Table 4.4.5-1 until the specific actiyfty of the primary coolant is restored to within its limit.
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('URVEILLANCE REOUIREMENTS 4.4.5 The specific activity of the reactor coolant shall be demonstr'ated to be within the lfmfts by performance of the sampling and analysis program of Table 4.4.5-1-.
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WASHINGTON NUCLEAR -.UNIT 2 3/4 4-16 L
R CTOR COOLANT SYSTEM
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3/4.4. 5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2-hour thyroid and ~hole body doses resulting from a main steam line failure outside the containment during steady-state operation 'will.not exceed small fractions of the dose guidelines of 10 CFR Part 100.
The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC 'of typical site locations.
These values are conserva-tive in that specific site parameters, such as SITE BOUNDARY location and meteorological conditions, were not considered in this evaluation.
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 0.2 micr'ocurie per gram DOSEZ)UIVALENT I-131, but less than or equal-to 4.0 micro-curies per gram DOSE E/UIVAL'EHT I-131, accommodates possible iodine spiking M
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Closing the main steam line isolation valves prevents the release of
'ctivity to the environs should a steam line rupture occbr outside containment.
The, surveillance requirements provide adequate assurance that excessive specific
- activity levels 'he reactor coolant wi11 be detected in sufficient time to take corrective action.
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6.9.1.5 Reports required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of station,'tility, and other personnel (including contractors)'.receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and gob functions" (e.g.';. reactor. operations and..
surveillance, inservice inspection, routine maintenance, special maintenance
)describe maintenancej, waste processing, and refueling).
The dose assignments to various duty functions may be estimated
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based on pocket dosimeter, thermoluminescent dosimeter (TLG), or, film badge measurements.
Small exposures totalling less than 20" of the individual total dose need not be accounted for.
Zn the aggregate, at'east 80>> of the total whole-body dose received from external sources should be assigned to specific ma)or work functions; and b.
Gocumentation of all challenges to main steam line safety/relief, valves.
MONTHLY OPERATING REPORTS 6.9.1.6 Routine reports of operating sties and shutdown experience shall be suomitted on a.monthly basi~
he Oirector, Office o'f Resource Management, U.S. Nuclear Regulatory ~issioa, washington, Q.C. 20555, with a copy to the Regional Admin'or of the Regional Office of the NRC, no later than the 15th of each ~
following the calendar month covered by the. report.
REPORTABLE
. CCURRENCEE
- 6. 9. 1. 7 0ELETEO FROHPT NOTIFICATION WIT+>I HRITTEH FOLLOHOP 6.9.1. 8 0ELETEO "This tabulation supplements the requirements of f20.407 of 10 CFR Part 20..
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No. 8
ENCLOSURE 2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM, WNP-2 SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE Functional Areas 1.
Management involvement in assuring quality.
Technical review of the submittal indicates that the management reviews are timely and technically appropriate.
Rating:
Category 1
2.
Approach to resolution of technical issues from a safety standpoint.
The=-licensee showed a general understanding of the technical issue and used acceptable approaches.
Rating:
Category 1
3.
Responsiveness to NRC Initiatives The licensee responded favorably to NRC initiatives.
Rating:
Category 2
4.
Staffing (including management)
N/A 5.
Reporting and analyses of reportable events N/A 6.
Training and effectiveness and qualification N/A 7.
Overall rating for functional area:
1.3
Reference:
NRC Manual Appendix 0516 - Systematic Assessment of Licensee Performance