ML20129E416
| ML20129E416 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/26/1983 |
| From: | Mccoy C NRC |
| To: | Pinto J NRC |
| Shared Package | |
| ML20129E334 | List: |
| References | |
| FOIA-84-665 NUDOCS 8507160814 | |
| Download: ML20129E416 (1) | |
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l M91 MEMO TO:
J. F. Pinto, Mahager, Nuclear Plant Engineering FROM:
C. K. McCoy, Nuclear Plant Manager
SUBJECT:
Penetration Closure PMI:
83/9537 Enclosed are marked-up copies of the penetration drawings which reflect the results of a walkdown of all buildings for unidentified or open penetrations.
These r. ark-ups also include physical as-built information that was observed during the course of this walkdown.
The closure of open penetrations, already shown on project drawings, is underway; and, the closure of unidentified penetrations is being processed for proper closeout.
These open penetrations have been evaluated for potential impact to nuclear heetup, and it has been deter =ined*that all safety bou.daries are intact and no safety implications exist as a result of these open penetrations.
Ei.peditious incorporation of this as-built information is required to support the penetration tagging operation which is to get underway as soon as possible.
These as-built drawings will be used as a final check
-during this tagging ef fort.
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. McCoy Plant Manager 8/26/83 CRH/CKM/vje
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Enclosure cc:
J. B. Richard J. P. McGaughy, Jr.
Project File Plant File File 8507160814 850403 s
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i se occasi Q lun Emotember
- 1. 19821 it w.s discovered that the 30 second closure timesj
[TTr1 tsor the scram discharge _ volume vent and drain valves were not verified i
ITTF1 las recuired by T.s.4.1.3 1
- prior to entry into Operational condition 21 O s 1(startup) on August 19, _.1'W2.
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d 13161 lthat time but foTT) !! June 23. 1983. determined the event should have been reported under l
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v cAuse wscsusmoas AaeoconstECTIVE ACTIONS h Q IThe operability requirements of T.S.4.1.3.1.4 were considered met by theg fTIT1loreep test prior to entry into Operational Condition 2.
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idetermined that T.S. step 4.1.3.1.4.a.1 was not performed. The test l
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[ Tech. Specs. for 4.0.4 applicability has been requested.
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NAME OF PREPARER PHONE
AttechEtnt to AECM-83/0410 Page 2 of 3 SUPPLEMENTARY INFORMATION TO LER 83-073/03 L-0 Mississippi Power & Light Company Grand Gulf Nuclear Station - Unit 1 Docket No. 50-416 i
Technical Specification Involved: 4.1.3.1.4 Reported Under Technical Specification: 6.9.1.13.c Event Narrative:
On September 1, 1982, it was discovered that all the requirements of Technical Specification Surveillance 4.1.3.1.4 were not completed prior to entry into Operational Condition 2 (Startup) for initial criticality on August 18, 1982.
I Surveillance 4.1.3.1.4 requires the scram discharge volume be determined operable by demonstrating:
a)
The scram discharge volume drain and vent valves operable, when control rods were scram tested from a normal control rod configuration less than or equal to 50% rod density at least once per 18 months by verifying that the vent and drain valves:
1)
Close within 30 seconds after receipt of a signal for control rods to scram, and 2)
Op'en when the:
a)
Scram signal is reset b)
Trip signal is bypassed The CRD preop test (IC11PT01 Revision 1) did scram the control rods from an all rods-out configuration and did verify that each rod fully inserted on the scram. However, it was not verified that the vent and drain valves shut within 30 seconds of receipt of the scram signal. Although the test did not explicitly verify that the valves reopened, af ter bypassing the Scram Discharge Volume High Water Level Bypass switches and resetting the scram signal, the steps did measure how long it took the scram discharge volume high water level scram and rod block signals to reset, thus indicating the drain valves were open.
Thus, the only part of the surveillance intent which was not met was measuring the vent and drain valve closure times on receipt of the scram signal. The conditions required to perform this test are not achievable at this time (50%
rod density).
l Technical Specification 4.0.1 and 4.0.4 state that surveillances must be completed prior to entry into an Operational Condition or while in the l
Operational Condition unless as "otherwise stated". Technical Specification t!
4.1.3.1.4 states that the scram discharge volume shall be determined operable via a scram test from less than or equal to 50% rod density. This was not L
Attechtint to
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AECM-83/0410 Page 3 of 3 attainable under current license restrictions (5% thermal power). Origina11y this incident was screened as not reportable. A scram test from a " normal control rod configuration of less than or equal to 50% rod d,ensity" was restricted by license conditions. A later evaluation on June 23, 1983, determined that the event should have been reported under Technical Specification 6.9.1.13.c.
Surveillance test 06-0P-1C11-R-0011 will perform this timing measurement when conditions allow. A change to Technical Specification 3.1.3.1 f or the applicability of Technical Specification 4.0.4 will be requested. This is submitted as a final report pursuant to Technical Specification 6.9.1.13.c.
The event had no affect on the health and safety of the public and did not constitute a threat to plant safety.
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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B O X 16 4 0. J A C K SO N, M I S S I S41 P P,1 3 9 2 0 5
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July 22, 1983 4 g,. O i
J u n u..,...c u.o, a Office of Inspection & Enforcement U. S. Nuclear Regulatory Comission Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30303 Attention:
Mr. J. P. O'Reilly, Regional Administrator
Dear Mr. O'Reilly:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. HPF-13 File 0260/L-835.0 Scram Discharge Volume Vent and Drain Valve Closure Times Not Verified Per Technical Specification Requirement LER 83-073/03 L-0 AECM-83/0410 On September 1, 1982, it was discovered that the thirty (30) second closure times for the scram discharge volume vent and drain valves were not verified as required by Technical Specification 4.1.3.1.4 prior to entry into Operational Condition 2 (Startup) on August 18, 1982. A plant incident report was written at that time but was screened as not reportable. A later evaluation on June 23, 1983, determined the event should have been reported.
Therefore, we are now reporting the event pursuant to Technical Specification 6.9.1.13.c.
Attached is LER 83-073/03 L-0 with Supplementary Information.
Yours truly,
/k bU F. ent cc:
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/5 Member Middle South Utilities System EXHIBIT 5