ML19253B257
| ML19253B257 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/27/1979 |
| From: | Andognini G BOSTON EDISON CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 79-191, NUDOCS 7910100167 | |
| Download: ML19253B257 (6) | |
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BOSTON EDISON COMPANY GEt* TRAL OrrtCEs 800 BovLsTON STREET JOSTON, Mass ACNumETTs 0 2199 G. CAnL ANDOGNIND S UPERINTEN DE N T NUCLE AN OPERATIDNS DEPARTMENT September 27, 1979 BECo. Ltr. #79-191 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA.
19406 License No. DPR-35 Docket No. 50-293 Annual Report of Tests, Changes or Experiments Performed at Pilgrim I
Dear Sir:
In accordance with 10 CFR 50.59(b), Boston Edison Cr.pany hereby submits a report containing a brief description and a summary of the safety evaluations of all modifications implemented and tests conducted at Pilgrim Nuclear Power Station between July 1, 1978 and July 1, 1979.
Very truly yours, l/
9:Ev:.n;
/
cc : Director Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Commission c/o Distribution Services Branch, DDC, ADM Washington, D. C.
20555 (40 copies)
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701025.0 g
1124 351
10 CFR 50.59 REPORTABLE PILGRIM NUCLEAR POWER STATICN MODIFICATIONS IMPLEMENTED BETWER JULY 1, 1978 AND JULY 1, 1979 The following are modifications to the Pilgrim Nuclear Power Station Unit #1 as described in the Safety "aalysis Report which were implemented between July 1, 1978 and July 1, 1979, under the authorization of 10 CFR 50.59(a) without prior Commission approval. Preceding the implementation of the modification, it was determined that:
1.
The modification would not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report; 2.
The modification would not create a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report; and 3.
The modification would not reduce the margin of safety as defined in the basis for any Technical Specification.
Water Shielded Viewing Windows (PDCR 78-18)
Water shielded viewing windows were installed in selected pump and tank room shield walls to permit both monitoring essential tank levels and detecting pump seal failures.
These windows decrease personnel radiation exposure by eliminating unnecessary entries to investigate equipment problems.
This change affects FSAR Figure 12.1-1.
- This change does not involve an unreviewed safety question as defined in 10 CFR 50.59 (a) or a change in Technical Specifications.
Recirculation Pump Suction Valves (PDCR 78-35)
The automatic closure feature was removed from the recirculation pumps suction valves MO-202-4A & 4B to assure that these valves remain open aiding vessel depressurization for LOCA when a piping break occurs between the recirculation pump suction and discharge valves.
This change affects FSAR Section 4.3.4
- This change does not involve an unreviewed safety question as defined in 10 CFR 50.59 (a) or a change in Technical Specifications.
I124 352
jhielding Walls (PDCR 78-M-14)
Concrete block walls were installed at various locations in the station to provide additional radiation shielding.
This change affects FSAR Figures 12.1-2 and 12.1-6.
- This change does not involve an unreviewed safety question as defined in 10 CFR 50.59 (a) or a change in Technical Specifications.
Control Rod Drive System Pressure Controller (PDCR 78-M-16)
An accumulator was added to the CRD supply pressure controller sensing line to dampen out oscillation in the process fluid used to control the valve.
This change affects FSAR Section 3.4 and Figures 11.8.1 and 11.9.1.
- This change does not involve an unreviewed safety question as defined in 10 CFR 50.59 (a) or a change in Technical Specifications.
Safety Related Snubbers (PDCR's 79-07, 07A, 07B & 07C)
In response to 1E Bulletin 79-07, a reanalysis was performed on the Main Steam System and the Reactor Recirculation System. This analysis was extended to the Residual Heat Removal System and the High Pressure Coolant Inj ection System.
Based on the results of the reanalysis, modifications were made to the relief valves of various safety related snubbers and both the snubber steel and the structural steel associated with safety related snubbers.
This change affects FSAR Sections 12.2 and 2.5.3.
- This change does not involve an unreviewed safety question as defined in 10 CFR 50.59 (a) or a change in Technical Specifications.
Drywell Floor & Equipment Sump Pumps (PDCR 79-M-6)
In response to IE Bulletin 79-08, the control logic for the drywell floor and equipment sump pumps was modified to eliminate the potential for an automatic transfer of water from the drywell.
This change affects FSAR Sections 5.2.4 and 9.2.
- This change does not involve an unreviewed safety question as defined in 10 CFR 50.59 (a) or a change in Technical Specifications.
1124 353
RHR & CS Testable Check Valve Bypass Valves (NOD Memo 79-457)
It has been theorized that a failure of a solenoid valve associated with the air operated bypass valves around the RHR and CS testable check valves could defect the containment isolation function of the testable check valves.
Therefore, SV-1001-95A & B, SV-1400-51A & B have been closed and the air supplies to the valves isolated.
Administrative controls have been establisned cc insure this isolation continues until the potential failure problem is resolved.
This affects FSAR Sections 5.2.3 and 7.3.1.
- This change does not involve an inreviewed safety question as defined in 10 CFR 50.59 (a) or a change in Technical Specifications.
FSAR Amendment 34 (NED Memo 79-253)
"In this reporting period, Boston Edison has reviewed the status of work previously performed and to be performed relative to FSAR Amendment 34.
Table 4 of the original Amendment 34 lists the electrical work originally intended tc '3e performed. All this work has been completed except for replacement of 2 valve motor operators.
The attached Table 1 lists additional cables that were relocated at the same time this work was accomplished.
A safety evaluation has been performed relative to the additional cables re-routed and it has becn determined that these changes do not involve an unreviewed safety que scion as defined in 10CFR50.59(c)."
FSAR Table 12.4.1 Update (NOD Memo 79-116)
Technical Specification Amendment #36, issued to Boston Edison Company, changed licensed conditions for receipt, possession, and use of special nuclear, source and byproduct material at Pilgrim Nuclear Power Station.
The NRC Safety Evaluation accompanying Amendment #36 required that the FSAR table which lists quantity limits for possession of source materials, be updated to reflect the latest source inventroy.
This affects FSAR Table 12.4.1
- This change does not involve an unreviewed safety question as defined in 10 CFR 50.59(a) or a change in Technical Specifications.
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TABLE 1 CABLES RELOCATED THAT WERE NOT INCLUDED IN ORIGINAL AMENDMLNT 34_
Scheme Cable No.
Circuit Function SBA603A*
RHR Pump 2033 Fceder SBA606A*
RHR Pump 203D Feeder SSD1021A*
250V DC MCC D9 Feeder SBD176A*
125V DC MCC 08 Feeder SBG14 BAH DG B Neutral Grounding Transformer Voltage Leads (Relocate)
SBAG09D DG B Control (Relocate)
SDA609E DG B Control (Relocate)
K31J DG B Control (Relocate)
SAD /31A*
RWCU Valve 1201 Feeder SAD 731D*
RWCU Valve 1201 Contro!
SAD 731F*
RWCU Valve 1201 Control SBNS25F Torus Atmosphere Temperature SATE 50473 Torus Temperature SBFT8127B Flow to Stack
- included in revisions identified in BLE-167, 2/1/74 1i24 355
O PDCR's Safety Evaluation Nos.
78-18 78-SE-14 78-35 555, 555A 78-M-14 78-SE-29 78-M-16 78-SE-32 79-07 636 79-07A 626 79-07B 625, 629, 635 79-07C 627, 628, 632, 634, 637 79-M-6 79-SE-13 Memo's N0D-79-457 631 NED-79-253 231 NOD 79-116 78-5 l124 356