ML19031B181
| ML19031B181 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/14/1977 |
| From: | Schneider F Public Service Electric & Gas Co |
| To: | O'Reilly J NRC/IE, NRC Region 1 |
| References | |
| LER 1976-025-01 | |
| Download: ML19031B181 (5) | |
Text
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Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/622-7000.
Production Mr. James P. O'Reilly Director of USNRC January 14, 1977 Off ice of Inspections and Enforcements Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. O'Reilly:
LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 76-25/3L Pursuant to the reqtiirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 76-25/3L.
This report is required within thirty (30) days of the occurrence.
CC:
Director, Office and Enforcement Director, Office Information and
- (3 copies) of Inspection
( 30 copies) of Management Program Control
-686
Report Number:
Rep~r,t--Da te:
Occurrence Date:
Facility 76-2S/3L.
92120/76 12/15/76 Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Reduction of shutdown margin during special test exceptions.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 2 operation, Plant temperature 547°F, Plant pressure 2235 psig, Low Power Physics Testing in progress.
DESCRIPTION OF OCCURRENCE:
On 12/15/76, while measuring stuck rod worth during low power physics testing, the "stuck" rod was moved to maintain the reactor critical 'in violation of the intent of Tech Spec L.C~O. paragraph 3.10.1.
The "stuck" rod, B-6, was moved from 228 steps to 197 steps.
Technical Specifications paragraph 3.10.1 Action Statement was implemented.
The reactor was immediately borated to return control rod B-6 to 228 steps and raise shutdown Bank A to 38 steps so that shutdown Bank A could control reactivity.
As soon as control rod B-6 returned to 228 steps, compliance with Technical Specification L.C.O. paragraph 3.10.l was returned and the Action Statement was terminated.
-DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
The cause of this occurrence was a slight over dilution of the Reactor Coolant boron concentration.
The amount of reactivity in moving control rod B-6 was approximately 23 pcm or about 2 ppm boron which is less-than the measurement uncertainty of boron titrations.
ANALYSIS OF OCCURRENCE:
With all full length control rods inserted and the reactor subcritical by less than the reactivity equivalent to that specified in Technical Specifications L.C.O. paragraph 3.1.1.1 available for trip insertion, boration was initiated until the shutdown margin required by Specifica-tion 3.1.1.1 was restored.
The reactor was under control at all times and at no time was there any hazard to the general public or site personnel.
CORRECTIVE ACTION:
This occurrence happened during the performance of SUP 80.6, Minimum Shutdown Verification and Stuck Rod Worth Measurements, which is a one -time performance and will not be performed again.
The procedure was correct and a dilution precaution was stated in the procedure.
The occurrence was due to personnel error.
The incident was reviewed by all control room operators and the need to pay attention to procedure pre-caution statements was stressed.
LER 76-25/3L _, -
FAILURE DATA:
This is the first occurrence of this type.
Eq~ipment identification is not applicable for this occurrence.
B. Canfield Manager -
SaEem Generating Station SORC Meeting No.
~~~~~~~~-
122-76
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. ~-
LICENSEE EVENT Rl:PORTe.
CONTROL BLOCK 6
LICENSEE 1..ICENSE EVENT NAME 1..ICENSE*NUM9ER TYPE:
TYPE
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57 sa 59 so 51 69 74 15 eveNT oeSCAIPTION
@lill During Mode 2 operation, while measuring stuck rod worth during low powet 7
89
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@ID I physics tes;ting, the "stµck" rod was m9ved to maintain the reactor justJ 7
8 9
@El critical in violation of the intent of Tech Spec L.C.O.*paragraph 3.10.L 7
8
@li] I The "Stuck" rod, B-6, was moved from 228 steps to 197 steps *. Tech Spec I 7
8 9
~I paragraph 3.* 10.1 Action Statement was implemented.
The reactor was
. 7
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PRIME SYSTEM CAUSE COMPONENT cooe cooe:
COMPONENT cooe SUPl"\\..IER
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COMPONENT MANUFACTURER I Z I 91919 I 44 47 VIOLATION l.NJ 48
@Ell The cause of this occurrence.was a slight over dilution of the reactor so I
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9 l.2illl coolant boron concentratipn.
7 8 9 The amqunt of 80 reactivjtv. in moving*.control I 8l
[@]I rod B-6 1
a s wa.s approximatelt 23 pcm or about 2 ppm boron which is less than I
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- STATUS
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10 12 1J FORM OF AC"TIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVl°TY GiJ
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- 10 11 PERSONNEL EXPOSURES METHOOOF DISCOVER¥ I l£.J 44 45 DISCOVERY OESCRIP'TION N/A 46 LOCATION OF REl..EASS:
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. DESCRIPTION
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9 N/A LOSS OR OAMAGE TO. FACILITY Eli] 19-:;j i°ESCRIPTION N/A 1
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a~9-------------------------U.,t-r:.~-------------------------------------------------Jao AOOITIONAL FACTORS (I01 EVENT DESCRIPTION AND CAUSE DESCRI.PTION Continued on page 2 7
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PHONE: (609) 365-7000 Ext.Salem-52 12/20/76 EVENT DESCRIPTION (Continued) immediately borated to return control rod B-6 to 228 steps and raise shutdoWn Bank A to 38 steps so that shutdown Bank A could control reactivity.
As soon as control rod B-6 returned to 228 steps, compliance with Technical Specification.
L.C.O. paragraph 3.10.1 was returned and the Action Statement was terminated.
Redundant reactivity control systems were available throughout this event.
This is the first occurrence of this type.
(76-25/76).
CAUSE DESCRIPTION (Continued) the measurement uncertainty of boron titrations.
The reactor was immediately borated to return control rod B-6 to 228 steps which terminated Technical Specification paragraph 3.10.1 Action Statement.
Manufacturers. nameplate data is not applicable for this occurrence.